Nuclear España - SNE · NUCLEAR ESPAÑA september 2013 5 INTRODUCTION N owadays, Nuclear Energy...

SPANISH NUCLEAR SOCIETY

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J O U R N A L O F S PA N I S H N U C L E A R P R O F E S S I O N A L S

IgnacioARALUCE

Director of the Paris WANO Center

INTERNATIONAL NUCLEAR MARKET

Nº 343. SEPTEMBER 2013

Edita SENDA EDITORIAL, S.A.

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www.sne.es JUNTA DIRECTIVAPresidente: Francisco LÓPEZ GARCÍA. Vicepresidente: José Ramón TORRALBO ESTRADA.Tesorero: Pedro ORTEGA PRIETO. Secretario General: Enrique PASTOR CALVO.Vocales: Antonio COLINO MARTÍNEZ, Luis Enrique HERRANZ PUEBLA, Pablo LEÓN LÓPEZ, Luis MARTÍNEZ ANTÓN, Emilio MÍNGUEZ TORRES, Juan ORTEGA DELGADO, Roque Luis PEREZAGUA LÓPEZ y Juan José SERNA GALÁN

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COMISIÓN DE PROGRAMASPresidente: Jesús FORNIELES REYES.Vocales: Alberto ABÁNADES VELASCO, Rodrigo CUESTA PÉREZ, Almudena DÍAZ MONTESINOS, Carlos GÓMEZ RODRÍGUEZ, Antonio GONZÁLEZ JIMÉNEZ, Ángel LOPERA, Adrián LÓPEZ MADRONES, Santiago LUCAS SORIANO, Andrés MUÑOZ CERVANTES, Manuel PRIETO URBANO, Alfonso VINUESA CARRETERO y José Mª ZAMARRÓN CASINELLO.

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COMISIÓN DE TERMINOLOGÍAPresidente: Alfonso DE LA TORRE FERNÁNDEZ DEL POZOVocales: Agustín ALONSO SANTOS, Leopoldo ANTOLÍN ÁLVAREZ, Eugeni BARANDALLA CORRONS, Miguel BARRACHINA GÓMEZ, José Luis BUTRAGUEÑO CASADO, José COBIÁN ROA, Luis PALACIOS SÚNICO y Ramón REVUELTA LAPIQUE.

COMISIÓN WINPresidenta: Isabel GÓMEZ BERNAL.Vicepresidenta: Mª Luisa GONZÁLEZ GONZÁLEZ.Vocales: Carolina AHNERT IGLESIAS, Inés GALLEGO CABEZÓN, Magdalena GÁLVEZ MORROS, Ma Teresa LÓPEZ CARBONELL, Aurora MARTÍNEZ ESPARZA, Matilde PELEGRÍ TORRES, Trinidad PÉREZ ALCAÑIZ, Ma Luisa PÉREZ-GRIFFO COCHO, Ma Luz TEJEDA ARROYO y Concepción TOCA GARRIDO.

COMITÉ ORGANIZADOR 39 REUNIÓN ANUALPresidenta: Montserrat GODALL VIUDEZ.Secretario: Pío CARMENA SERVERT. Tesorero: Gonzalo ARMENGOL GARCÍA.Presidenta del Comité Técnico: Pilar LÓPEZ FERNÁNDEZ.Vocales: Julio BELINCHÓN VERGARA, Mariano CARRETER ULECIA, José Luis ELVIRO PEÑA, Manuel FERNÁNDEZ ORDOÑEZ, Maribel GÁLVEZ PALERO, Francisco GONZÁLEZ DE LA PEÑA, Antonio GONZÁLEZ JIMÉNEZ, Raquel OCHOA VALERO, Enrique PASTOR CALVO, Matilde PELEGRÍ TORRES, Pilar SÁNCHEZ BARRENO, Teresa SÁNCHEZ SANTAMARÍA, Francisco Javier VILLAR VERA y Eugeni VIVES LAFLOR.

COMITÉ TÉCNICO 39 REUNIÓN ANUALPresidenta: Pilar LÓPEZ FERNÁNDEZ.Secretaria Técnica: Lola PATIÑO RAMOS.Vocales: Juan B. BLÁZQUEZ MARTÍNEZ, Alfredo BRUN JAÉN, Eva María CELMA GONZÁLEZ-NICOLÁS, Elena DE LA FUENTE ARIAS, Alberto ESCRIVÁ CASTELLS, Laura GALA DELGADO, Francisco GARCÍA ACOSTA, Andrés GÓMEZ NAVARRO, Marisa GONZÁLEZ GONZÁLEZ, Carlos LAGE PÉREZ, Ricardo MORENO ESCUDERO, Silvia ORTEGA LES, Juan José REGIDOR IPIÑA, Rafael RUBIO MONTAÑA y Marta VÁZQUEZ CABEZUDO


ENTIDAD DE UT I L IDAD PÚBL ICA

Nuclear EspañaJOURNAL OF SPANISH NUCLEAR PROFESSIONALS

SUMMARY

4 EDITORIAL

5 INTRODUCTION 7 INTERVIEW Ignacio ARALUCE. Director of the Paris WANO Center

INTERNATIONAL NUCLEAR MARKET 10 TECNATOM, a Spanish engineering in a global market Íñigo Loizaga, Luis Rejas & Ramón Izquierdo

21 The Spanish Nuclear Group for Cooperation: A story of success Carmelo Palacios

27 Spanish Nuclear Safety Research under International Frameworks Luis E. Herranz, Francesc Raventós, Carolina Ahnert, Gonzalo Jimenez, César Queral, Gumersindo Verdú, Rafael Miró & Sergio Gallardo

35 On-Site Field Services Mariano Rodríguez Aycart, Emilio Bobo Pérez, Luis Pascual Rodríguez, Alejandro Merino Teillet, Ignacio Martínez Gozalo, Jose Tomás Ruiz, Marcelo Soto Tomás & Sergi Vilanova Cuadrado

47 Co-operation in the development of a policy and strategy for the management of spent nuclear fuel (including provisions for its safe interim storage) and radioactive waste in Mexico Pablo Zuloaga, Mariano Molina, J. Bárcena, EVA Salas , Moisés Sánchez, H. Codée & J. Deckers

53 The evolution of nuclear energy. Opportunities for the industry Maria Teresa Domínguez

58 NEWS OF THE WORLD

EDITORIALIn recent months, we have been

witness to important regulatory developments that have had, or are

going to have, a significant impact on the evolution and future of the Span-ish nuclear fleet. Together with law 15/2012 containing fiscal measures for energy sustainability, including a 7% tax on electric power production and, more importantly, another tax associ-ated with spent nuclear fuel produc-tion, which have led to a dispropor-tionate increase in the costs associated with nuclear power generation and the early cessation of operation at the Santa María de Garoña nuclear power plant, two new regulatory proposals have been submitted: the new Nucle-ar Safety Directive of the European Atomic Energy Community (Euratom) and the draft Royal Decree for respon-sible, safe management of spent nucle-ar fuel and radioactive waste.

The first of these proposals involves a revision of the current Directive 2009/71 on nuclear safety, the transpo-sition period of which expired in July 2011 and which establishes a commu-nity framework for the nuclear safety of nuclear facilities and is consistent with the IAEA Convention on Nuclear Safety and with the rules of this organ-ization, which are not binding. This Directive revision by the Commission is only logical after the Fukushima ac-cident, as it will incorporate the lessons learned from the accident itself and also from the results of the stress tests performed by all the member status. After studying the draft that has been circulated, there are some reasons for concern, e.g. the excessive degree of technical detail in some areas, bearing in mind that this is a framework reg-ulation, and the fact that little impor-tance is given to specific national reg-

ulatory bodies, which even opens up the possibility of intervention by out-side member states in national com-petencies and perhaps conflicts with the principle of subsidiarity. Likewise, the proposed draft could weaken the principle of independence of the na-tional regulatory bodies with respect to the political powers, given the role assigned to the European Commis-sion. We have no doubt about the con-gruence of this directive revision for the reasons given hereinabove, and we hope that in the revision process the opinions that will help make the new directive better than the current one will be taken into account so as to improve the safety and development of our nuclear industry and to make the normal development of this energy option compatible in those states that decide to use it, maintaining the high safety standards that society deserves to expect from these facilities. We must not forget that the nuclear option is recognized by the EU as beneficial for the security of supply and to mitigate the greenhouse effect, and it leaves it up to the sovereign decision of each member state.

The second proposal, the draft Royal Decree for responsible, safe manage-ment of spent nuclear fuel and radio-active waste, which aims to transpose Directive 2011/70 on fuel and waste management,together with other mod-ifications of a lesser scope, includes in its first final provision a modification of the regulation on nuclear and ra-dioactive facilities (RINR) enacted by Royal Decree 1836/1999 of December 3. This modification of the current RINR includes the requirement for a finan-cial guarantee to cover the costs and contingencies stemming from the dis-mantling and decommissioning pro-

cess, and the most significant modifi-cation changes the original wording of the RINR (“final cessation”) to “cessa-tion”, and one year is allowed to apply for the operating license renewal when the cessation is not due to reasons of nuclear safety or radiological protec-tion. This latter modification, which opens up a new door to application for the renewal of the Santa María de Ga-roña operating license, is undoubtedly good news after the enormous uncer-tainties faced by the entire nuclear sec-tor, and especially by all the people di-rectly involved in this project that has been under way for more than 42 years with so far the very best safety and re-liability standards, as the SNE has con-firmed on several previous occasions.

As we have seen, these new regulato-ry proposals shed light and shadow on the evolution of the Spanish nucle-ar fleet, and therefore we must keep a careful eye on the definitive versions in order to quantify their final impact. On our part, we would like to appeal to the commitment and responsibility of all the social players involved in these processes so that the final wording of these regulations will make it possible to increase even more, if possible, the safety of the nuclear power plants in Spain and Europe and to support the safe, reliable and economically profit-able operation of the Spanish nuclear power plants, which clearly yield enor-mous benefits in terms of the security of supply and mitigation of the green-house effect and have a significant positive effect – both directly and indi-rectly – on the country’s economy and employment.

The New Nuclear SafeTy DirecTive aND The DrafT of The royal Decree focuSeD oN loNg-Term operaTioN

Board of Directors ■

NUCLEAR ESPAÑA september 2013 5

INTRODUCTION

Nowadays, Nuclear Energy represents 13.5 % of the world’s electricity produc-tion, having 69 new nuclear plants under

construction in 14 countries. In Spain the Nuclear Power represented 20.58 % of the total electricity production last 2012, which has been an average value over the last years. In our country, there is no plan of new constructions and the last Unit was connected to the grid at the end of the 80 s.

After more than 20 years of construction, the Spanish industry had to change from construc-tions to operations, from starting-up to field ac-tivities support, and engineering for construction to design change modification engineering. This change was not enough to absorb the huge quali-fied workforce. Therefore, part of the Spanish Nu-clear Industry was re-oriented to the International Market or International Research and Develop-ment.

Some of those Spanish companies are supporting outages performing fuel inspection, Pumps & Mo-tors inspections and repairs, chemical cleanings in France, Belgium, Slovenia, Switzerland, Italy…etc, even South America is a mature market for some of our companies for this business line.

On the other hand, Spanish operational instruc-tors are well-known and recognized world-wide. The Spanish industry is providing train-ing around the world and expanding this highly skilled know-how to new markets such as United States, Brazil, Argentina, China and United Arab

Emirates. There is also a well-establish educa-tion in nuclear at the Universities and Research Centers, that attracts many international students every year.

In all these years, other working lines had to be created such as waste management and D&D business. El Cabril, the Spanish Low and Interme-diated Waste Disposal was designed & construct-ed from scratch providing the know-how to the Spanish industry which currently is exported as is shown in this issue.

Last but not least, Nuclear R&D in Spain is in a well-known international position thanks to a group of extremely dynamic, enthusiastic and pro-active researchers who are keeping a valu-able heritage of more than 60 years of Nuclear Research in Spain. Taking into account the current cutbacks to support the research institutions and Universities in Spain, it is highly praiseworthy their collaboration in the most important interna-tional research projects.

In general, this special number shows some of the international projects around the world and how the vision and the effort provided by our pro-fessionals have resulted into a wide portfolio of nuclear capabilities and a very qualified personnel available to support any field activity engineering design or material supply. Therefore, the Spanish professionals, researchers, material and products are having more and more visibility in the inter-national framework.

iNTerNaTioNal Nuclear marKeT

Nuclear España ■


Ignacio AraluceDirector of the Paris WANO Center

Ignacio Araluce is a physicist who majored in fundamental physics, and he has a Master’s degree from the former Junta de Energía Nuclear.He began his professional career in 1979 in Tecnatom, where he obtained the license of Nuclear Facility Supervisor, and he trained the first teams of operators of the second generation of nuclear power plants.In 1981 he joined Almaraz NPP as head of operations and five years later became head of production. In 1988 he was appointed plant director, a post he held until December 31, 2001. After that he was Director of the DTN and from there moved to Slovakia to direct the Bohunice plant support project.In 2006 he was named director of the Paris WANO Center.

INTERVIEW

The experience of the Spanish nuclear industry and its professionals is internationally recognized. For this reason, this issue of Nuclear España has an extraordinary distribution in various markets and is being published in English for greater circulation in countries with nuclear interests. One of the most well known Spanish professionals in international organizations is Ignacio Araluce. As Director of the Paris WANO Center, he has talked to us about the most important initiatives of this association, which is an umbrella organization for the operators of all the world’s nuclear power plants.

wANo, A uNiQue experieNce

After the Chernobyl accident, nucle-ar operators around the world pro-posed that an international, private association be created in order to improve nuclear safety and reliabil-ity at all the facilities. Thus was the World Association of Nuclear Oper-ators born in 1989 for the purpose of setting the best industry standards, “which are independent of those set by the nuclear regulatory bodies, the governments of different nations and the International Atomic Energy Agency”, says the director of WANO Paris, Ignacio Araluce.

This is done by exchanging know-how and experience. And the fact is “there is no competition in the field of nuclear safety, we exchange all the experiences. We believe that a plant that functions perfectly well can al-ways be improved”, says Araluce.

As for organization, the Associa-tion is structured around five centers: four operating centers (Atlanta, Paris, Moscow and Tokyo) and one coordi-nation and supervision center located in London, where the practices of all the centers are unified.

At this time, WANO is the only worldwide organization where all

the world’s nuclear power plants are associated under one umbrel-la. In 2006, nuclear fuel reprocess-ing plants were also allowed to join WANO as members.

According to Ignacio Araluce, the Association’s funding is an example of its independence. “The WANO budget comes from its members.

There is no competition in the field of nuclear safety, we exchange all the experiences ■

8 NUCLEAR ESPAÑA september 2013

ENTREVISTA

The qualification process, which will classify the plants by levels, will be ready in WANO Paris by 2015 ■

They are the ones that make the de-cisions”, says the general director of the Paris center.

New experieNces After fukushimA

The accident in the Japanese plant of Fukushima in 2011 has led to the performance of stress tests, one re-sult of which has been the imple-mentat ion of improvement pro-grams in facilities around the world.

From the very beginning, WANO was asked to take part in the discus-sions about the stress tests, which “were very demanding on the op-erators. It is important to note that from the beginning, the operators were very involved in the process and were the first ones interested in learning everything possible from the accident so that their facilities would be increasingly safer”, says Araluce.

In addition to the collaboration given by WANO to the regulatory bodies to prepare the stress tests, the Association reacted very quickly, says the general director of the Paris center. “Before the stress tests were made public, we drew up a signif-icant operating experience report with recommendations to be imple-mented in all the world’s plants. Fur-thermore, before we knew in detail the subsequent evolution and con-sequences of the accident, we were able to suggest a series of lessons learned, primarily about the miti-gation of consequences”. Since then, several documents have also been issued, with recommendations that the operators must implement and which will be reviewed by WANO to ensure compliance.

A New structureThe Fukushima accident has not on-ly led to the implementation of im-provement programs in the plants. As Ignacio Araluce points out, “a committee was set up to analyze the influence of the accident on WANO’s programs and strategies. This com-mittee has been working for over a year and has submitted its conclu-sions to the Association’s biennial meeting which took place in China,


with a recommendation to the Board of Directors that was in turn submit-ted to the members’ General Assem-bly, which approved some resolu-tions that have had and are having a very significant impact”, says the general director of the Paris center.

Thanks to these agreements, the WANO staff will be increased four-fold by 2016. For example, “three years ago, 29 engineers worked in the Paris center, along with admin-istrative and other categories of per-sonnel; two years later we have 94 engineers and in another two years we will have 145. We are increasing our capabilities dramatically”, says Araluce, who stresses the following actions:• The frequency of the Peer Review

missions has been increased from 6 to 4 years

• An internal Peer Review has been carried out to ascertain what has to be improved in the regional centers

• A very important emergency pre-paredness and accident conse-quence mitigation project has been established

• A project to integrate design into all WANO activities is being de-veloped, and one of the objectives in all the reviews is that the plant design margins be maintained all through the operating life and, when a design modification is im-plemented, it will have previously been approved by the competent design authorityAraluce says that, although it is

true that the stress tests have in-volved a considerable workload for the plants, at the same time the plants have not neglected their daily obligations because “the operator has to strike the right balance so as not to lose an operational focus, since the most important thing is for the plant to operate well every day”.

plANt QuAlificAtioNOne of the recommendations of the WANO Board of Directors, made during its meeting held in the Chi-nese city of Shenzhen, was that the

The Spanish sector has a consolidated operating record, with tremendous prestige abroad and comparable to the best in the world ■

Key WANO ProgramsConsidering that safety is the top priority of nuclear power plants opera-tors, WANO has four key programs:• OPERATING EXPERIENCE. This was the first program to be devel-

oped and is the backbone and foundational reason of WANO. Under this program, the nuclear power plants send to WANO all reports considered to be of interest, especially those regarding accidents and incidents; WANO then studies them and forwards the conclusions to all members. At present, this Association has a database of more than 6,000 reports. In addition, two times a year, it makes an in-depth study of special relevance for which it sends an international team to the plant where the incident has occurred in order to draw conclusions that can be useful for the other operators. This type of document con-tains recommendations that must compulsorily be implemented by all the members.

• PEER REVIEW PROCESS. This is the program that requires the most resources. It is an observation-based diagnostic process carried out by teams formed by professionals from different fields. All the plants are reviewed in according with objective operating criteria, and when the three-week review has been completed, a report is drawn up identify-ing the areas for improvement with respect to the best industry stand-ards and the best practices. Before the Fukushima accident, the reviews were conducted every six years with an intermediate review at three years. The frequency has recently been increased and the facilities are reviewed every four years with an intermediate review at two years. “The Peer Reviews are considered by the operators as an effective tool”, says Araluce.

• TECHNICAL ASSISTANCE, BEST PRACTICES AND OPERATING INDICATORS. Once the areas for improvement are detected in a plant, an action plan should be implemented. For this purpose, the Association contacts the rest of the operators and creates a team of experts, who are representatives of operators that have had a similar problem and have solved it, and they contact the plant that requires support. Based on operating indicators, all the plants can compare their main parameter results with the rest of the plants in the world.

• PROFESSIONAL DEVELOPMENT AND TRAINING. This initiative is intended to support leadership programs in the facilities and create discussion forums on certain issues of common concern to the plants.

ENTREVISTA

Association undertake an assessment process, similar to the one run by IN-PO in the United States, as a comple-ment to the Peer Reviews and that would conclude with qualification of the plants.

“In principle, the agreement in WANO is that this plant assessment process be carried out when the four operational centers in the world have a similar level in terms of quality of resources”, explains Araluce. “Our Board of Directors has asked us from Shenzhen to begin to develop that process”.

At this time, the criteria on which the final qualification of each of the plants is going to be based are de-fined, as are the elements to be tak-en into consideration on assessing their nuclear safety and reliability. In this way, all the world’s plants will be classified at 4 or 5 levels, “a qualifi-cation that will be internal to WANO and will not be made public because the purpose, as always, is to exchange information between operators to im-prove plant operation”, says the gen-eral director of the Paris center.

This initiative is intended to identi-fy those units around the world that most urgently need help. “This pro-cess will allow all of us as operators to prioritize our support activities to the plants that most need assistance, which is something that INPO, with which we are jointly working, is do-ing in the United States and, conse-quently, the criteria will be very sim-ilar.

The qualification process is in the test phase and is due to be imple-mented in 2015.

the future of NucleAr power worldwide Ignacio Araluce has extensive inter-national experience and is very fa-miliar with the development of the nuclear industry. In this respect, he acknowledges that “this is not exactly the right time to talk about the future of nuclear power in Europe”. Fukus-hima has had a great impact on Eu-rope, “although not based on techni-cal reasons. The most negative effects have been in Germany, but also in countries such as Italy, Belgium and Switzerland”.

However, the situation is mixed. For instance, in the United Kingdom, the governmental institutions clearly support nuclear power. The planned program, which promotes nuclear energy, is moving forward and is in good health, just as in countries like Russia and Ukraine. There is also very significant interest in the Middle

East: the United Arab Emirates, Saudi Arabia, Jordan”.

Araluce says that “the economic cri-sis that Europe is experiencing – but that is not affecting other regions of the world – has influenced nuclear power for several reasons, including reduced demand on one hand and an increase in capital costs and financing difficulties on the other. This means that nuclear power, which is capi-tal-intensive, suffers from the effects to a greater extent”.

spAiN ANd iNterNAtioNAl recogNitioNSpain has not escaped this general at-mosphere that affects Europe. But ac-cording to Ignacio Araluce the country has an important advantage, which is that “it has a consolidated operat-ing record, with tremendous prestige abroad and comparable to the best of the world’s rankings, which serves as a point of reference for many operators from different countries”.

“Furthermore, we have our own nuclear industry and a very good, fully independent regulatory body of international renown. In general,

Spain has very strong foundations which, in my opinion, will enable the nuclear facilities not only to reach the end of the normally established lifetime in good condition, but also to obtain a life extension as is happen-ing in other advanced countries in the world”, says Araluce.

He also recognizes that there are factors that distort this future. “That is the case of Garoña which, with an impeccable operating record, has been affected by decisions that make it economically unviable”.

In any event, Araluce is clear on saying that “it is not admissible to consider an energy production mix in which nuclear energy is not a major component, since it contributes to a very significant strategic independ-ence. It should be remembered that when a nuclear reactor is loaded, it has fuel for 18 months or two years, which provides great stability not on-ly to the operator but also to the na-tion as a whole. Because of all these factors and when things are again calmer for decision making, nucle-ar energy will undoubtedly have a bright future”, says Araluce.



Tecnatom, a Spanish engineering in a global marketI. Loizaga, L. Rejas & R. Izquierdo

Tecnatom has been successfully developing its activities for more than fifty years thanks to a fully committed working team, its working capacity and its orientation toward innovation.

During the past years, a set of skills and expertise have been developed focusing upon the international market. Nowadays, Tecnatom is carrying on its activities in countries such as United States, Brazil, Argentina, China and United Arab Emir-ates to name but a few. The activities carried out here cover an ample range of tasks. Tecnatom is involved in the initial and continuous training of operational staff not only in facilities already in commercial operation but also in green field developments. Technical support during commissioning, emergency readiness plans drawing, development of innovative aids for operations and designing and developing main control rooms and full scope simulators are other mainstream projects on the way.

INTroDUCTIoN

Since Tecnatom was founded it has been providing its services, exper-tise and know-how to the Spanish Nuclear Industry. In fact, Tecnatom has not only been involved in the domestic developments but also has taken part in some punctual pro-jects overseas. Taking advantage of the experience gained; at the end of the last decade the Company took the strategic decision to offer its ex-pertise in a personalised attention to its international customers wherev-er they could be needed.

This decision has given us the opportunity to work in different cultural environments, under different legislation frameworks and for diverse corporations. In oth-er words it has eventually allowed us to learn and put in practice the best industry practices, to enhance our performance, to develop better customer-oriented products and to strengthen our decision making capacity. All in all having a better grasp of our international custom-er’s problems and eventually pour-ing the acquired know-how into our national nuclear industry.

As a result, the internationaliza-tion strategy results in Tecnatom making an effort of sizing and re-

cruiting a new work force and the establishment of the Internation-al Training Centre (ITC) as a new branch of Tecnatom Nuclear Train-ing area.

INTErNATIoNAl TrAININg CENTrE

The International Training Centre was initially established in 2011, af-ter it was drafted four years previ-ous. By then a new hiring campaign was undertaken in order to gather, select, hire and train the best possi-ble workers for the challenge.

The International Training Cen-tre mission is to deliver training with the best technical and educa-tional experiences, in the most ef-ficient time periods and at the best cost-benefit for customers. This demanding objective can only be achieved thanks to a flexible struc-ture, team-work, decision-making ability and independence from oth-er internal structures. Putting these qualities together allowed us to answer any training request, any-where and, in most cases, exceeding customer expectations.

Thirty instructors trained in the state-of-the-art nuclear technologies - AP-1000, KWU, PWR, BWR, are the core of the team. However, support from other training centres along

IñIgo LoIzagais Industrial Engineer in Energy and Executive MBA by Instituto de Empresa, Madrid. He joins Tecnatom in 1991 qualified as “Senior Reactor Operator” and with more than twenty years of experience in Nuclear Power plant Training, working several years as instructor and different training projects.He is currently heading the International Training Centre in Tecnatom.

LuIs Rejasis a mining engineer, Master degree, specializing in Energy and Fuels, joins Tecnatom in 1996 obtaining the qualification of “Senior Reactor Operator” in PWR-3 loops. He has developed his career synchronizing tasks operating personnel training and implementation of HFE in new reactors. Since 2009, he is the head of the department of design of new control room.

Ramón IzquIeRdois aeronautical engineer for the UPM. He works in Tecnatom since 1990. He is currently Simulation Senior Engineer.He has participated in several NPP simulators development (Zorita, Almaraz, Vandellos, Trillo, Laguna Verde, Garoña, Atucha II, etc.). He has worked as a developer of model builder tools as well.


INTErNATIoNAl NUClEAr mArkET

Figure 1. Training Organization.

Figure 2. International Instructors.

Figure 3. Systematic Approach to Training.

Today part of the team consists of fourteen AP-1000 Senior Reactor Operator Instructors certified by Westinghouse Corporation. These highly experienced instructors combined their activities among the Chinese Nuclear Power Plants under commission in Haiyang and Sanmen sites, in the offices of West-inghouse in Cramberry, Pensylvana, United States and in our headquar-ters in Madrid, San Sebastian de los Reyes. Figure 2.

This group has followed a demand-ing training programme in order to become operation instructors of Gen-II nuclear technology and, sub-sequently, were trained as operation instructors of AP-1000 Technology.

So far, among the projects they have been involved are the devel-opment of training material for the Operation and Maintenance Sup-port Engineers using the System-atic Approach to Training (SAT) methodology, the design of training programs for Maintenance Techni-cians, Operation Supervisors and Operation and Maintenance Sup-port Engineers. They have delivered

training for Non-Licensed personnel as well as train-ing for Reactor Operators and Senior Reactor Oper-ators through theoretical and full scope Simulator training in the Chinese nu-clear power plants. Finally AP-1000 Instructors work in the Certified Training for AP1000 Vogtle plant in the USA. Figure 3.

The International Training Centre also has a team of five nuclear operation instruc-tors who carry out their day to day activities in the Unit-ed Arab Emirates (UAE), specifically in Abu Dhabi.

with the availability of assistance from subject matter experts makes the International Training Centre fully capable of undertaking any project. Figure 1.

Some of the international in-structors have started their careers within one of the Spanish training areas and after a successful time were considered to be-come part of the thrilling ITC project, however a number of these instruc-tors have been recruit-ed, selected, hired and trained to face Interna-tional Projects.

Tecnatom runs an in-house selection depart-ment to carry out the screening, selection, and hiring of people with the particular qualities sought. The selection pro-cess takes as its basis a well-defined Job Profile. Here, intellectual apti-tudes, personality, atti-

tude towards work, and organisa-tional culture styles are analysed.

Here there is only room for high-ly motivated, globally available and goal-oriented instructors that face each overseas project as an oppor-tunity to increase nuclear safety and spread their knowledge and cultural heritage.


For this particular project a cus-tomized Nuclear Training Prepara-tory Course has been designed, developed and implemented. The course aims to develop students’ ba-sic skill and knowledge for comple-tion of Nuclear Power Plant training and qualification. This course is ad-dressed to future Reactor Operators, Senior Reactor Operators and Engi-neers of the Barakah Nuclear Power Plant.

The project was started in mid-2012 and is expected to last until mid-2014. During this time more than two hundred engineers and technicians from the UAE receive a nuclearization course. It not only en-ables them to face, with confidence, the rest of the training period but also introduces them to the nuclear behavioural expectations and safety culture standards

Today, five more instructors from the ITC are dealing with the training

of Angra NPP in Brazil at different levels. They are involved in the in-itial training of Reactor Operators, Senior Reactor Operators and Op-eration Instructors. CN Angra also relies upon the requalification of its operation crews in the full scope simulator as well as the training of the NPP managers. Figure 4.

The collaboration between Tecnatom and Angra NPP dates back more than twenty year. Now-adays, it has been intensified due to the generational change and new regulatory requirements.

The good relationship between CN Angra and Tecnatom has im-plied that on many occasions; Tecnatom has acted as a link be-tween Brazilian nuclear power plants and Spanish nuclear facili-ties. The objective has always been to find a successful solution, usually through benchmarking, to common problems such as, the digitization of

the Control Room or the review of procedures, to name but a few.

The ITC activities are not only re-lated to the training area. The team is also responsible for providing technical support to those Nuclear Facilities beyond the Spanish bor-ders. In this regard, another group of instructors are helping with the commissioning of the Atucha II nu-clear plant in Argentina.

Another activity that is carried out by the ITC instructors for ATUCHA NPPs is the methodological training of their team of instructors. ITC pro-vides them with the know-how, skills development and required knowl-edge to deliver training in an out-standing way to the operation shifts and oversight the activities of NASA’s instructors during the full scope sim-ulator and theoretical session.

Its training, the deep knowledge of nuclear plant systems and operation, the experience gained in past and cur-rent projects drawing and reviewing operating procedures, the experience working with full-scope simulators makes this team of nuclear instruc-tors’ ideal for this type of work.

To conclude, features like personal-ity, principles, resilience, social skills and the ability to manage relation-ships are necessary traits to cope with the global challenges. All of them have been taken into account when selecting this group of professionals. So far the ITC involves instructors from three different nations Spain, United Kingdom and the United States. Figure 5.

The international experience gained serves also as a benchmark in the domestic market. It allows as-sessing and noting the high degree of qualifications achieved by the instruc-tors and their flexibility to address tai-lored-to-needs training programs.

Today the International Training Centre instructors are present in five geographic areas – Europe, Middle East, Asia, North America and South America. Becoming a trustworthy company has required persistence and innovative approaches to prob-lems faced. However, keeping their confidence would be even more de-manding. Performing a better job every day is our vision and our chal-lenge.

TrAININg SUpporT. INTErNATIoNAl NUClEAr powEr plANT SImUlATorS

Simulation is an essential technol-ogy for training, operation and en-gineer support in which Tecnatom has over thirty years of experience.

Figure 4. Angra NPP.

Figure 5. Features for a Global Challenge.


INTErNATIoNAl NUClEAr mArkET

As a result, the construction of sim-ulators for training purposes is one of the main aspects of Tecnatom’s business.

In the last fifteen years, Tecnatom has focused on diversifying and ex-panding its services in the training area, meaning that its participation in the construction of internation-al nuclear power plant simulators has increased significantly. At the end of nineties and the start of the new century, Tecnatom actively collaborated with the construction of simulators in Lugmen (Gongliao, Taiwan) and Laguna Verde (Verac-ruz, México). The successful results in both collaborations consolidated Tecnatom’s position in internation-al simulation projects, therefore generating the necessary desire to undertake new international ad-ventures.

In February 2010 NASA (Nucl-eoeléctrica Argentina S.A.), the pub-lic company owner of the nuclear power plants in Argentina, award-ed Tecnatom with the construction of the full scope control room repli-ca simulator for Atucha II.

Furthermore, at the end of 2011, Tecnatom won the international tender promoted by the company ELECTROBRAS -ELECTRONU-CLEAR, owner and operator of nu-clear power plants in Brazil, for the construction of the control room simulator for Angra I.

Both contracts confirm not only the technical and economic com-petitiveness of Tecnatom at inter-national level, but also its increas-ing presence in the Latin American market.

The scope of both projects in-cluded the supply of a full size

control room replica simulator and, for Atucha II, also the supply of a Classroom Simulator (Interactive Graphic Simulator) based on vir-tual panels and process diagrams. The duration of these projects was committed to being thirty six months for Atucha II and thirty four months for Angra I. This meant that the projects ran consecutively there was in fact a short overlap between them.

The development of the simu-lation models that reproduce the systems of both plants and how they are operated from the control room, were carried out entirely in Tecnatom by project teams made up of over thirty people, including engineers from the awarded Com-panies. Tecnatom addressed these projects using its own technology that has been continuously devel-oped and updated since the 1980s in order to achieve a high level of fidelity under the strict compliance with normative and international standards.

At the same time as the devel-opment of simulation software programs, all of the panels and instruments that were to exactly reproduce the interface of the con-trol room were being constructed. To complete the installation, Tec-natom’s interface system was inte-grated in the simulator.

It goes without saying that, in or-der to carry out projects with such characteristics as these, it was nec-essary to hire new technical work-ers. For all of the new young people with university degrees, resources, language skills and, for the major-ity, their first working experience, a specific and in-depth training in

nuclear technology was required as well as training in the simula-tion programs and tools imple-mented in Tecnatom.

This training process encour-aged the professional and personal development of these new young engineers, allowing them to evolve inside and outside of Tecnatom.

The continuity in time for both projects allowed Tecnatom to “re-use” the new engineers, continuing the advantage of having them on board. This meant that, when the Atucha II project ended its devel-opment phase, these trained and experienced engineers were little by little transferred to the project of Angra I. This continuity avoid-ed carrying out the traumatic and slow recruitment process for new staff. Figure 6.

For Tecnatom, these two large and challenging projects have rep-resented a qualitative leap in the areas of technology, methodology and human resource management and training. It has also allowed a quantitative leap to be made in the number of people who are directly or indirectly involved in these ar-eas. But the latter aspect has also provided a “lifting” effect in the staff and caused an accentuate re-juvenating effect that allows the company to have a young, dynam-ic, motivated, qualified and pas-sionate organization that guaran-tees the generational replacement in a slow manner.

HFE ANAlySIS: opErATINg DISplAyS AND mAIN CoNTrol roomS DESIgN

Since the “Three Mile Island” ac-cident, Human Factor Engineering (HFE) application to the design of Nuclear Operator’s work plac-es, main control rooms, mimic instrumentation panels, and op-eration displays has proved to be an effective method for reducing human error during Plant Oper-ation. Since the nineties interna-tional organizations have adopted this technique as a necessary tool to ensure safe operation standards and to minimize the occurrence of human errors.

Tecnatom’s participation in the development of safer operation started in the early nineties, with projects like AP600 with Westing-house, or FOAKE and Lungmen with General Electric, but it was in 2009 when the decision for the internationalization of Tecnatom

Figure 6. Atucha II Simulator Project Team.


at a global level was made. In that year Tecnatom started working on several projects in parallel, such as two units of South Texas Project (STP) with Westinghouse, as well as eight units and three full scope simulators (Fuqing 1-4, Fangji-ashan 1-2, Hainan 1-2, and their corresponding three simulators). Figure 7.

The scope of these projects in-cludes design, fabrication, integra-tion, V&V, and testing, based on the Human Factors Engineering, of the control rooms (consoles, mimics, remote shutdown panels etc.) as well as the system operat-ing displays for normal operation, and operation in case of failures or emergency. On top of this, the pro-jects cover operation supporting systems such as computer based procedures, alarm engineering (filtering and prioritization), or the design of special systems like the SPDS (Safety Parameter Display System).

All of the above works have been carried out with a strict adherence to both European and American international regulations. This has been done by developing our own methodologies and tools, which have been optimized to achieve very competitive products in the world market that have been li-censed in countries like USA, Chi-na, Taiwan, Brazil,…

These activities, carried out in a brief time frame, have been a big challenge for Tecnatom. Once again, they have required an en-hancement of staff members, ad-dressed by hiring young nuclear engineers who are well prepared

and knowledgeable but lacking in previous experience. In order to meet the demanding requirements of the projects, a big effort has been made in these years with impor-tant investments in both econom-ical and human resources. During this time we have always kept in mind our goal of having a stable staff unit of engineers with high levels of training and knowledge in nuclear power plant operation. As well as this, we have always taken advantage of the lessons learned in the projects carried out in the international market, allow-ing us to provide high added value services to the Spanish NPP fleet.

The initial difficulties of em-ploying young personnel when these projects began have now be-come one of the biggest strengths of the company as the projects are successfully coming to an end. It means that Tecnatom currently has a high percentage of engineers of less than thirty five years old with-in its staff, all of whom have more than five years experience in the design, fabrication, and startup of the new Reactors Control Rooms.

These projects have consolidat-ed and reinforced the position of Tecnatom as a company recog-nized worldwide, consolidating its leadership in the nuclear business and allowing us to advance to-wards important projects such as for the granting of important pro-jects for our group as the Electrical Power Research Institute (EPRI) Human Factor Guides revision. Additionally, we have achieved the right to attend international con-ventions of the American Nuclear

Society (ANS), International Elec-trotechnical Commission (IEC), or the EPRI working group ANT (Advanced Nuclear Technology) amongst others.

The future is still to be written but in Tecnatom we will keep on working on the advanced reac-tor’s continuity and diversifying our activities in other types of reactors such as the fusion reac-tors, the Small Modular Reactors (SMR), or the High Temperature Reactors. It may even be possi-ble to expand into other Industry sectors where Safety Culture is especially important such as the aerospace market, immediate re-sponse centers, radwaste storage facilities, or conventional power plants.

CoNClUSIoNS

Internationalization has brought a sustainable work force increase. Around 300 people have been hired, trained and are growing professionally day by day. It is at the heart of Tecnatom to help them reach whatever goals they have but always keeping the em-ployees aligned with the corpo-rate values that are the corner-stone of the company.

Going global is understood by Tecnatom as an opportunity to create value, to bring the best workers in and that eventually benefits also our national custom-ers. Close contact with interna-tional markets boost innovation. In other words, the quality and commitment of the team allows them to be able to do their best so as to resolve and succeed in com-plex situations.

Internationalization is a privi-leged observatory for identifying and anticipating future industri-al needs. What is more, it is the place to be in order to develop new products and services, to ex-change know-how and to gener-ate a contact network for rapid re-sponse to any situation in which it is required.

To conclude, Tecnatom commit-ment towards internationalization is firm. It has meant an important investment in human capital and in designing and developing new products and services through in-novative approaches that have led to strengthen the foundations of Tecnatom and also have boosted the position of Spanish NPP with-in the world.

Figure 7. Fangjiashan NPP simulator.


The Spanish Nuclear Group for Cooperation: A Story of SuccessC. Palacios

The SNGC (Spanish Nuclear Group for Cooperation) is an alliance founded in 2006 for commercial cooperation between Spanish nuclear companies in order to join ef-forts for the commercial promotion in the Chinese market. This alliance was original-ly formed by Enusa Industrias Avanzadas S.A. (ENUSA), Tecnatom S.A. and Equipos Nucleares S.A. (ENSA). In 2008 Ringo Válvulas S.L. joined the alliance, and in July 2008 the Nuclear Group for China AIE was incorporated with each of the four com-panies holding a 25% share. Subsequently, as explained below, the legal name was changed to Spanish Nuclear Group for Cooperation AIE and the trade name of Span-ish Nuclear Group/China was maintained as a brand for activities in this country.

Spanish companies that manufacture nuclear equipment and have synergic activities are represented in the SNGC and this is why they are interested in taking part in it.

The SNGC is open to temporary or permanent collaborative initiatives with other Spanish companies in the nuclear sector, whether or not they are equipment manu-facturers, to boost the Spanish nuclear industry’s presence in China or other emerg-ing countries.

Its incorporation in July 2008 was motivated by the expectations for strong growth presented by the Chinese market (which is in the lead of the worldwide nuclear renaissance, as China has 17 operating nuclear power plants, more than 27 under construction and others in the design phase, and the country currently shows a need for this energy to be able to maintain its long-term industrial capacity; around 58 reactors will be operative in 2020 and 31 will be under construction that year), as well as by the experience that some of the partners had at that time in supplying equipment and technology to this market.

In this context, the SNGC partners have important synergies thanks to the fact that their product and service portfolios complement each other and to the previous suc-cessful experiences in specific collaborations between them on both the national and international markets.

With the creation of this consortium, these four Spanish companies aim to develop and secure their business internationally, primarily in a constantly growing market of great strategic importance such as China. The consortium enables the partners to optimize their commercial efforts and complement their product and service of-ferings so as to provide their clients with more integrated, competitive products and services. In addition, it has helped consolidate the Spanish companies that are mem-bers of SNGC AIE as a substantial group in the global nuclear industry. Another very important point that was considered is market size and the fact that the corporate group would help achieve a critical mass that would make the partners visible both to potential customers and to the Spanish Administration.

Spanish nuclear companies have been operating in the Chinese market for 25 years, ever since they first attended the Beijing Nuclear Trade Show in 1987. This event ended with a fantastic trip inside China that we will remember all our lives and that was organized by the Chinese Nuclear Society, with visits to the nuclear facilities in Xian, Sichuan and Shanghai.

By 1989, the Spanish nuclear companies were separately offering in China the fol-lowing goods and services: operator training, steam generators, fuel transport casks, valves, irradiated fuel pool storage racks, heat exchangers, control rooms and their simulations, pre-service and in-service reactor inspections, fuel inspection equip-ment, etc.

After all those years, the four Spanish nuclear companies decided in 2006 to join efforts to, first of all, jointly approach the Chinese market (Spanish Nuclear Group for China) and later the group was expanded to other countries and was renamed Spanish Nuclear Group for Cooperation.

CARMELO PALACIOSis an Industrial Engineer with a degree from the Polytechnic University of Madrid; he also has an MBA in economic sciences from the Universidad Complutense of Madrid.He has spent almost his entire professional career as a commercial executive in the field of nuclear energy, mainly in Equipos Nucleares S.A. (ENSA ) where he reached the position of Vice-President for Business Development .He is currently the General Manager of SNGC.

MEMBER CoMpANIES of ThE SNGC

The Spanish companies are ENSA, ENUSA, RINGO VÁLVULAS and TECNATOM (see Figure 1).

Although they are well known throughout the nuclear world, fol-lowing is a brief summary of their key businesses. A detailed descrip-tion of their capabilities is provided hereinafter.

ENSA: Manufacturer of large, heavy equipment to strict quality requirements. Primarily NSSS com-ponents: reactor vessel, steam gener-ators, etc., as well as fresh and spent fuel racks and casks. Service Divi-sion: Maintenance services, contin-gencies and repairs.

ENUSA: Fuel manufacturer. Complete reload & core design, ad-vanced core & fuel design, fresh & irradiated fuel management, on-site fuel service, in-service tests & in-spections.

RINGO VALVULAS: Manu-facturer of high quality valves for nuclear power plants (and other facilities with highly demanding requirements, e.g. cryogenic instal-lations).

TECNATOM: Wide range PSI & ISI services portfolio, NDT & Robotic


INTERNATIoNAL NUCLEAR MARkET

Figure 1.

Table 1. Products and services that the SNGC can offer.

MAIN pRodUCTS ANd SERVICES SUppLIEd By ThE SNGC CoMpANIES

Table 1 is a schematic illustration of the most important products and services that the SNGC can offer.

JoINT SNGC ACTIVITIESThe joint SNGC activities can be summarized as follows:•Generalmarketingefforts.•Marketingcoordination.•Commercialpromotion.•Participationinexhibitions.•Delegationcoordination,including

delegations of Chinese clients visit-ing our companies in Spain and of joint visits by SNGC members to Chinese companies in China.

•Marketnewsresearchandscope.•SNGCnewsletterpublicationand

distribution. •Newopportunities.Newalliances,

etc.•Finance.Exportcredits,etc.•Governmentprograms.•TheSNGChasalocalstaffinBei-

jing for follow-up, contacts, mar-keting, etc. in China.

details of Some Activities:

Trade FairsIn all these years, the SNGC mem-bers have taken part in the different Chinese nuclear trade shows, usual-ly together with the Spanish Nuclear Forum, an organization that repre-sents the interests of most Spanish nuclear companies, and supported by the Spanish Institute of Foreign Trade (ICEX).

This year, 2013, the fair has been held in Shanghai.In2012thefairwasheldinBeijing.In 2011 the fair was held in Shen-

zhen. Figure 2 show some photos of this fair.

From April 6th to 8th 2011, the four companies of the SNGC – ENSA, ENUSA, RINGO VÁLVU-LAS and TECNATOM – partici-pated in the International Nuclear Exhibition 2011 held in Shenzhen(Guangdong) in the Popular Re-public of China. The group was supported by the “Foro de Industria Nuclear Española” and the Spanish State Agency ICEX.

In the booth, the four companies of the SNGC displayed their capabil-ities and references for the supply of equipment and services for nuclear power plants. The booth was vis-ited by a large number of Chinese nuclear entities in search of further collaboration in Chinese nuclear de-velopment.

Technology Development, ISI equip-ment manufacture, Operation & Maintenance training, planning of engineering support, Control Rooms, Simulation & Testing.

hISToRy of ThE SNGC

The history of the SNGC can be brief-ly summarized as follows:•2006:Alliancebetween

- ENSA - ENUSA - TECNATOM

•March2008:RINGO- RINGO included in the alliance

•July2008:Consortium- Formally incorporated as a part-

nership according to the Spanish legal figure “Asociacion de In-terés Económico – AIE”.

•May2010:- Extension to other countries

(Spanish Nuclear Group for Co-operation), mainly:- India- Latin America- South Africa

MAIN fACTS ABoUT ThE CoNSoRTIUM oRGANIzATIoN

The consortium organization can be summarized as follows:•Commercialalliance,non-profit.•Legalentity:Consortium.•Contracts awarded to the compa-

nies, not to SNGC. •President:rotatesamongthecom-

panies. •VicePresident:formerPresident.•FulltimeGM:formerENSAVPforBD.

•Administrative, other supportfrom the companies

•OfficeinBeijing

ENSA ENUSA TECNATOM RINGO

•Designengineering. √ √ √ √

•NSSScomponents,spentfuelcasks and racks. √ √

•Licensing. √ √ √ √

•Constructionandstart-up √ √

•Nuclearfuelcycle. √

•Pre-ServiceandIn-Serviceinspection and testing. √ √

•Controlroomsandsimulators √

•NPPoperationsupport. √ √ √

•Outageservices. √ √ √

•NPPMaintenance. √ √ √ √

•Valvecomponents. √

•Sparepartmanagement. √ √

•Nuclearwasteanddecommissioning. √ √

•Newreactors. √ √ √ √


This is all meant to underline the excellent level of collaborationwiththe Spanish Nuclear forum and the ICEX

Chinese Delegations in SpainOne of the most important activi-ties the SNGC has carried out over the years has been to welcome Chi-nese nuclear industry delegations in Spain. There have been more than 30 delegations.

Signature of Collaboration Agreements (MOU)Over the years, more than 10 MOUs have been signed with various Chi-nese agencies and companies, meet-ings have been held and major con-tracts have been awarded. Some of these MOUs are as follows:•Xi’anNuclearEquipmentCo.Ltd.

(XNE), capital goods manufactur-er.

•ChinaNuclearPowerResearchIn-stitute (CNPRI).

•China Jianzhong Nuclear FuelCorp. (CJNF),which operates theYibin nuclear fuel factory.

•CNNC broad scope MoU SNGCGeneral Agreement with CNEA at Shenzhen.

•NPICMoU for irradiated fuel in-spection equipment.

•SuzhouNuclearPowerInstitute•China Technology Engineering

Company. •NuclearPowerInstituteofChina.

Figures 3,4 & 5 shows some of the signing ceremonies.

Chinese InternationalizationAlso of great interest is the aim of Chinese nuclear companies to internationalize and the poten-tial alliances they could enter into with the Spanish nuclear industry/SNGC.

The four companies wish to in-tensify the collaboration with the Chinese market in the ambitious nuclear program that China is de-veloping. Once again, and this has been recognized by our Chinese cli-ents on several occasions with their orders, we underline our strengths in this Chinese nuclear market: quality and experience, technolog-ical independence and flexibilityand a medium size that comple-ments the capabilities of the Chi-nese industry.

Internal Weekly News Bulletin and Fact Sheets

Of special mention is the news bul-letin that SNGC issues on a weekly basisfortheexclusiveuseofitspart-

ners. Its purpose is to report in great detail, and with the greatest possible market orientation, the nuclear news on our target markets published that week.

On the other hand, the group periodically issues, for its mem-bers’ use, fact sheets on differentnuclear power sectors and organi-zations in the countries covered by the group’s activities. These factsheets are available to all the mem-bers in a cloud computing appli-cation, along with all the data on our contacts (current and potential customers).

Website and Newsletter

The SNGC maintains a very active Web-site – www.sngc.es – in Chinese and English that we invite anyone to visit.

Very recently we have launched this same Website only in Chinese but from a Chinese server: www.sngc.com.cn. We invite our Chinese clients to visit this website as it will be easy for them to access.

We are also distributing a newslet-ter every two months to our current and potential customers in our line of business which reports on the mem-ber companies’ main accomplish-ments during those two months.

Figure 2. ICEX/FORUM/SNGC Stand in the 2011 Shenzhen Nuclear Trade Show

Figure 3. ENSA’s former President and SEC Director Yu Jian Guo sign the contract for the Sanmen steam generator supply (AP-1000) in the presence of former Spanish Government President Mr. Rodríguez Zapatero and the current China State Council Prime Minister, Li Kequiang. (January 2011)


INTERNATIoNAL NUCLEAR MARkET

oThER dETAILS oN ThE SNGC CoMpANIES

General

Some noteworthy points include the following:– The highly competitive Chinese

market due to the presence there oftheworld’sleadingsuppliers,aswell as the already very developed local enterprises prepared to com-pete on the international market.

– Thediversityofexistingplantde-signs in China that requires tech-nological, regulatory adaptation, etc., to be able to take part in ten-ders and that evidences the com-petitiveness of the Spanish capital goods industry.

– The benchmarking this entails for the SNGC member companies.

Workforce

Further details about the group companies include the combined workforce, which is summarized in Figure 5.

Capabilities and Technology Transfer

The technology transfer & localiza-tion capabilities are important for the group. These can be summarized as follows:

TECNATOM•Pre-service&in-serviceinspection

and testing engineering. •Qualification and dedicated en-

gineering of Safety Class compo-nents.

•Development and supply of con-trol rooms and simulators.

•Training management of licensedpersonnel & non-licensed/plant staff.

•Plant life management and plantlifeextensionprograms.

ENUSA•Advanced fueldesignandmanu-

facturing.•Fuel manufacturing and inspec-

tion technology and equipment.•On-site fuel handling, inspection

and repair.

ENSA•Steam Generators, Reactor Pres-

sure Vessels and Internals manu-facturing.

•Spent Fuel Racks and Casks andFresh Fuel Casks manufacturing.

•NPP repair andmaintenance ser-vices and procedures.

•NPP waste management equip-ment supply and techniques and procedures.

•Design,manufacturing,supplyandinstallationofheatexchangers.

RINGO VALVULAS•NuclearSafety-relatedvalveman-

ufacturing•Sparepartsandvalvesservices.

This capability and support for technology transfer have already been demonstrated in ENSA projects (manufacturing of steam generators and racks) and TECNATOM pro-jects (incorporation of a joint inspec-tion company as explained aboveand creation of a wholly owned TECNATOMfirminChinatodesigncontrol rooms and simulators).

International Experience of the SNGC Companies

Historical Experience

The SNGC members companies havediverseWorldwideExperience@ NPPs.•Referencesinmorethan35countries•Covering all current reactor tech-nologies: BWR, CANDU, PWR,VVER, etc.

More than 2,000 nuclear professionals

University Degree

500

400

300

200

100

ENUSA ENSA TECNATOM RINGO0

Specialists

AdministrativePersonnel

Figures 3 & 4. SNGC signs agreement with CNEA at Shenzhen in March 2011 (left) and Sig-ning Ceremony of the Cooperation Agreement between Tecnatom and NPIC. 2009 (right).

Figure 5.

Figure 6.


•Proven participation in designand construction of parts for new reactors –ABWR, EPR,AP-1000,HTR,etc.–withhighlyqualifiedstaff according to several national standards

•Equipment&componentdeliveryand services provisionThe worldwide presence of SNGC Members at New Nuclear Projects is very important, as seen in Fig-ure 6.

Worldwide Presence of SNGC Mem-bers at New Nuclear Projects

Infigure7youwillfindinterestinginformation about the participation of the Spanish Nuclear Group for Cooperation in new nuclear projects around the world.

CoNTRACTS AWARdEd To SNGC CoMpANIES IN ChINA

Following are the purchase orders obtained to date by the four group companies in the Chinese market:

TECNATOM– QinshanIoperatorstraining– Joint Venture CITEC: PSI/ISI

Ling Ao I and II NPP and all new CPR1000 after Ling Ao

– Control rooms for Fuqing, Fangi-anshan and Hainan NPPs.

– NPIC Electric penetrations for Eu-ropean NPPs.

ENSA– Steam generators for Qinshan II

NPP units 1- 4

– Spent fuel racks for Ling Ao 3&4.– Spent fuel transport cask for Daya BaytoLanzhou.

– Hainan NPP steam generators. – TaishanNPP(EPR)heatexchang-

ers.– Sanmen steam generators.

RINGO– Qinshan1&2valves.– Spare parts for CNEIC

ENUSA– Fuel rod ultrasonic inspection

equipment for the Yibin Fuel Plant.We should also mention in par-

ticular that one of our compa-nies – TECNATOM – has set up a joint venture – CITEC – with the Guangdong Group subsidiary named SNPI Suzhou Nuclear Pow-er Research Institute – SNPI – for inspection of nuclear power plant main components, reactor vessels, steam generators, etc.; this venture is operating very successfully and has performed the PSI/ISI in all the CGN Group plants. TECNATOM has also opened an office (Repre-sentative Office) in Beijing whichvery shortly will become a Whol-ly Owned Foreign Enterprise – WOFE – of TECNATOM under Chinese law and where around 20 Chinese engineers work. We can also say that, of the 17

reactors that are currently oper-ating in China, 9 have equipment or services supplied by the group companies. And of the 28 reac-

tors under construction in China, there are, for the time being, 9 that will have equipment and services provided by the group compa-nies, and to these we should add the equipment for the Yibin Fuel Plant.

CoNCLUSIoNS

The SNGC, as we have seen above, is not a supplier. The member companies are the suppliers.The SNGC is aBusinessDevel-

opment tool for the four compa-nies and it boosts the capacity of the four companies to be present in the emerging markets.

In conclusion, following are some arguments to choose SNGC members companies as a supplier:•Widerangeofcapabilities,prod-

ucts and services.•Capabilitiescovering:•NSSS•Fuel•MainComponents.•Independentfromleadingorigi-

nal equipment manufacturers•Innovative technologies and

modern facilities•Offering advanced in-house

technologies for NPP and new reactors

•Capable/focusedontechnologytransfer to local organizations

•Collaborative models based oninternational cooperation.

NEW REACTORS (IN RED) WHERE SNGC MEMBERS ARE PARTICIPATING

USA & CENTRAL AMERICAAP1000: 4 under construction+6 under developmentESBW: 4 under developmentABWR: 2 under developmentOTHER: 1 under construction and 1 under development

ARGENTINAPHWR: 1 under constructionPWR: 1 under development CANDU: 1 under developmentCAREM: 1 under construction

EUROPEEPR: 2 under construction & 4 under developmentVVER: 10 under construction CANDU: 2 under developmentABWR: 6 under development ITER & JHR: 2 under construction

CHINA & OTHER ASIAN COUNTRIESCPR: 20 under construction + 14 under developmentCNP600: 2 under constructionAP1000: 4 under constructionEPR: 2 under constructionABWR: 2 under construction

MIDDLE EAST & SOUTH AFRICAAPWR: 2 under constructionAPWR: 2 under developmentVVE: 4 under developmentATMEA: 1 under developmentNEW REACTORS: 2 under projectOTHERS: 22 under development

BRAZIL

PWR: 1 under developmentNEW REACTORS: 4 under project

Figure 7.


Spanish Nuclear Safety Research under International FrameworksL. E. Herranz, F. Raventós, C. Ahnert, G. Jimenez, C. Queral, G. Verdú, R. Miró, & S. Gallardo

The international nature of the investigation conducted by the Unit of Nuclear Safety Research

(UNSR) of CIEMAT, responds to the belief that international cooperation is the only efficient way for address-ing a so complex area. Namely, inter-national involvement is seen by CIE-MAT as an indispensable instrument to meet its generic objectives:• To develop, validate and assimi-

late methodologies of risk assess-ment.

• To reduce existing uncertainties in postulated accidents.However this heavy international

component, UNSR activities build up a bridge between worldwide fore-front research and its results applica-tion in a domestic environment. This is the major driver for CIEMAT’s col-laboration with the Spanish nuclear industry and institutions.

Three are the areas of investigation CIEMAT is presently addressing: severe accidents, nuclear fuel ther-mo-mechanics and safety of innova-tive nuclear systems.

RECENT UNSR RESULTS UNdER INTERNATIONAL PROJECTS

During the last 5 years CIEMAT has been participating in a good number of international projects. Besides, the just born projects in which UNSR is participating will be introduced.

Severe Accidents

The main projects shaping CIE-MAT’s research in the area of severe accidents have been: PHEBUS-FP,

SARNET, OECD-SFP, OECD-BIP, OECD-CCVM and ARTIST. The first two were launched under the EUR-ATOM framework program, where-as the next three have been framed under the OECD-NEA; the last one was an international project led by PSI.

The PHEBUS-FP (Clément & Zey-en, 2013) used a scaled down facili-ty (1:5000 with respect to a 900 MW French PWR) to conduct a total of 5 experiments (4 of them with spent fuel). Outstanding insights have been gained into fuel degradation, fission products transport and io-dine chemistry. CIEMAT has been contributing in the pre- and post-test analysis of containment phe-nomena with codes like CONTAIN 2.0, IODE 5.1, MELCOR 1.8.6 and ASTEC 2.0. Based on this work an extensive validation has been car-ried out and major observations, like the dominant contribution of sedimentation in aerosol deposition or the effective trapping of iodine by oxidized silver in the aqueous pond of containment, have been consistently estimated. It is worth mentioning the comparison set be-tween the major findings concern-ing containment iodine behavior within the PHEBUS-FP tests and the NUREG-1465 (Herranz & Clément, 2010b). The experience gained with-in the project was the basis for an as-sessment of how significant iodine chemistry might be in NPP source term estimates (Herranz et al., 2009). Complementary to PHEBUS-FP ex-perience, the International Source

CIEMAT: LuIs E. HErrAnzuPC: FrAnCEsC rAvEnTósuPM: CAroLInA AHnErT, GonzALo JIMEnEz, CésAr QuErALuPv: GuMErsIndo vErdú, rAFAEL MIró, sErGIo GALLArdo

The Nuclear Safety research requires a wide international collaboration of sev-eral involved groups. In this sense this paper pretends to show several examples of the Nuclear Safety research under international frameworks that is being per-formed in different Universities and Research Institutions like CIEMAT, Univer-sitat Politècnica de Catalunya (UPC), Universidad Politécnica de Madrid (UPM) and Universitat Politècnica de València (UPV).

Term Project was launched to ex-plain and deepen into some of the PHEBUS observations.

Since 2004 most severe accident investigation has been articulat-ed through the SARNET project (Van-Dorsselaere et al., 2012). The major issues addressed within this network of excellence were: corium coolability, core-concrete interac-tion, steam explosions and hydro-gen combustion in the containment and source term. Most of data ob-tained through experiments have been stored in a database called DATANET and the models devel-oped and validated are being im-plemented in the next version of the ASTEC code (2.0 r3). CIEMAT has been involved in several activities with particular emphasis in those related to source term. Significant contributions have been already published as for aerosol evolution (Herranz et al., 2010a) and iodine chemistry (Dickinson et al., 2010). As a consequence of these SARNET analytical activities, CIEMAT has conducted an extensive validation of the ASTEC and the MELCOR codes (Kljenak et al., 2010; Girault et al., 2012).

The OECD-NEA projects have addressed different issues: SFP, fuel degradation under anticipat-ed conditions during a complete LOCA (Loss Of Coolant Accident) in spent fuel pools; BIP, organic io-dides generation and iodine-paints interactions; CCVM, validation ma-trix for containment codes. Within the OECD-SFP project, the UNSR

CIEMAT


INTERNATIONAL NUCLEAR MARkET

Thermo-mechanics of nuclear fuel

CIEMAT has two major national collaboration agreements on nucle-ar fuel thermo-mechanics, one with CSN and the other with ENRESA. Some of their activities have a do-mestic scope, but there are others of an international nature related to projects like OECD-HALDEN, OECD-CABRI and OECD-SCIP (fo-cused on fuel behavior under steady and transient conditions); addi-tionally, a close follow-up is being conducted of the ESCP (focused on fuel extended storage) program. Ac-cess to the data resulting from these frameworks comes from the CSN in-volvement in the international pro-jects.

Data from HALDEN experiments have been used for many years to improve and validate codes like FRAPCON-3. Since 2012 CIEMAT has launched an activity to assess the FRAPTRAN-1.4 predictability of the fuel thermo-mechanics under LOCA conditions. Through the analyses of the LOCA experiments, major code drawbacks and needs will be iden-tified and, potential improvements to be made in the short and medium term will be defined.

CIEMAT’s experience on fuel transient behavior under RIA (Re-activity Insertion Accident) condi-tions has been gained within the CABRI project. Post-test analysis and preliminary analysis of the up-coming LWR-RIA tests has fostered technical exchange among partners. The best example is the RIA bench-mark organized under the frame of the international project, which has been articulated in 9 RIA scenarios based on tests already conducted or to be conducted of the CABRI and the Japanese NSRR program. CIE-MAT contributed to the benchmark by analyzing those scenarios with FRAPTRAN-1.4 and SCANAIR-7.1 (Sagrado et al., 2013). As a result of this work an extensive and deep comparison of thermal, mechanical and fission product transport mod-els responses has been made.

SCIP has been supplying data for years on irradiated BWR and PWR mechanical behavior. Through them a better understanding of the poten-tial cladding failures by pellet-clad-ding interaction and hydrogen-re-lated phenomena has been gained. Additionally, a sound database on clad ramping has been set up and two benchmarks have been recent-ly organized. In addition to techni-cal contributions with FRAPCON-3

built-up MELCOR models for BWR and PWR fuels for two fuel configu-rations, “hot neighbor” (i.e., no radial thermal radiation from the fuel cell) and “cold neighbor” (i.e., periphery fuel assemblies heated up by the cen-tral one). This work allowed identify-ing strengths and weaknesses of the code when addressing these scenari-os (Herranz et al., 2013). Key elements of the modeling were the hydraulics of air going upward through the fuel assembly, the zirconium oxidation by air and the thermal radiation heat transfer. Under the OECD-BIP frame-work, a sound database has been ob-tained and CIEMAT has proposed an empirical approach accounting for the different kinetics observed of the organic iodides production (Her-ranz et al., 2010). The OECD-CCVM project allowed gathering relevant experimental work that might be the bases for validation of contain-ment codes and/or modules of in-tegral codes; specific contributions were made from CIEMAT as for the identification and definition of key in-containment phenomena and the description of relevant experimental data in areas such as aerosol removal in leakage paths and aerosol resus-pension and reentrainment.

The ARTIST projects have inves-tigated the potential retention of fis-sion products within the secondary side of the steam generator during a meltdown SGTR sequence (Gün-tay et al., 2004). CIEMAT’s activities have been experimental and analyt-ical. Experimentally, CIEMAT has complemented the project database by measuring particle retention in the break stage of the steam gener-ator. More than 30 tests have been conducted in the LASS (Laborato-ry for Analysis of Safety Systems) of CIEMAT, in which the effects of particle nature, breach type and size and gas mass flow rate have been ex-plored. Consistently with other part-ners’ findings, major insights have been gained: even in the worst sce-nario, some mass retention should be expected in the break stage; particle nature largely determines mass trap-ping; largely agglomerated particles may undergo fragmentation due to tangential fluid stresses and colli-sions against tubes; etc. These and many other results have been report-ed by Herranz et al. (2006), Sánchez et al. (2010) and Delgado et al. (2013). On the analytical side, the main achievement has been the develop-ment and validation of a semi-empir-ical model, called ARI3SG, capable of predicting in-break stage aerosol

deposition (Herranz et al., 2007; Her-ranz et al., 2012; López et al., 2012).

In addition to the above projects, CIEMAT is participating in some other international projects recently launched under the frame of the 7th FWP of EURATOM. This is the case of PASSAM and CESAM. Even though research on severe accident manage-ment is one of the main pillars of both projects, PASSAM is mostly em-pirical while CESAM is entirely ana-lytical. PASSAM main goal is to set up a data base on the performance of existing and innovative systems for source term mitigation. Fission products retention in aqueous ponds and in sand filters will be investigat-ed under realistic challenging condi-tions still unexplored or poorly char-acterized, like water saturation or jet injection regime. Also, performance of innovative systems as pre-filter acoustic agglomerators, electrostatic precipitators, high pressure sprays and improved performance zeolites are to be tested under prevailing conditions in case of containment venting. The intention is to gather a sound database useful to enhance the potential performance of filtered containment venting systems. CIE-MAT has focused their activities on aqueous ponds retention under jet injection regime and on the particle growth resulting from an acoustic agglomerator.

CESAM is entirely focused on de-velopment of the ASTEC code mod-els and extension of its analytical ca-pabilities to different reactor designs. CIEMAT is contributing through preparation of a generic input deck for a BWR plant, modeling the BWR fuel degradation tests conducted by Sandia simulating a complete LOCA accident in a spent fuel pool and assessing and improving mod-els dealing with pool scrubbing, air oxidation of Zr alloys and thermal radiation in spent fuel pool configu-rations.

Finally, less than one year ago, CIE-MAT joined the OECD-BSAF project (Benchmark Study of Accident at the Fukushima Daiichi Nuclear Power Station), through the bilateral project with CSN for severe accidents. The project aim is to reach a deep under-standing of the scenarios, with par-ticular emphasis on identifying the governing phenomena and the final status of the units 1-3. CIEMAT is building up MELCOR 2.1 models for each of the units. The results of each participant will be discussed and the conclusions are planned to be used for the units decommissioning.


and FRAPTRAN codes, CIEMAT has been deeply involved in the co-ordination of both exercises. Some analyses have been conducted with FRAPCON-3.3 and some others with FRAPTRAN-1.4; this way the capa-bility of these two codes to capture phenomena in the time range of ramps has been checked (ramp tim-ing is right in between steady state and RIA, which are the natural do-mains of FRAPCON-3 and FRAP-TRAN -1, respectively). Herranz et al. (2011) reported in detail results and major outcomes of the first ex-ercise.

Safety of innovative nuclear systems

Since the early 90’s, CIEMAT has been working on innovative as-pects of safety systems of new re-actor designs. The studies evolved from modeling of passive systems performance of Generation III reac-tors to accident analysis of Genera-tion IV reactors. From 2005 to 2009, CIEMAT focused on High Temper-ature Reactors (HTRs) through 6th EURATOM projects, like RAPHA-EL, and through bilateral contracts with PBMR (Fontanet et al., 2009). However, last years the interest has moved to safety of Sodium Fast Re-actors (SFRs). In that environment, CIEMAT has been working on source term studies under the frame of the CP-ESFR project of the 7th EURAT-OM FWP. The project addressed key design aspects of an SFR, from the configuration (pool vs. loop) to the most suitable power cycle to be cou-pled (Rankine vs. Brayton), going through safety aspects. In this spe-cific regard, a critical assessment of what was known and unknown and an identification of the major needs in terms of model development were the first task undertaken by Herranz et al. (2012b).

Presently, CIEMAT is heavily in-volved in developing and validat-ing models considered fundamental for source term prediction. That is the case of sodium vapor nucleation under anticipated conditions of SFR containments in case of a BDBA (Be-yond Design Basis Accident). This work together with the develop-ment of a semi-empirical law for SFR cladding creep and the assessment of a modified version of RELAP-5 against sodium thermal-hydraulic tests (conducted in collaboration with UPV), are the major tasks of CIEMAT within the JASMIN project of the 7th EURATOM FWP. The final aim of the project as a whole is to en-

able the ASTEC platform to also ad-dress SFR accident scenarios.

REFERENCES• Clément B., Zeyen R.,The objec-

tives of the PHEBUS-FP experi-mental programme and main find-ings, Annals of Nuclear Energy, 2013 (http://dx.doi.org/10.1016/j.anucene. 2013.03.37).

• Delgado R., Herranz L.E., Attenu-ation of radioactive releases from NPP under accident conditions: An experimental research on risk-dominant scenarios, Chemical Engineering Research and Design 91, 603-613, 2013.

• Dickinson S., Andreo F., Karkela T., Ball J., Bosland L., Cantrel L., Funke F., Girault N., Holm J., , Her-ranz L.E., Housiadas C., Ducros G., Mun C., Sabroux J.-C., Weber G., Recent advances on contain-ment iodine chemistry, Progress in Nuclear energy 52, 128-135, 2010.

• Fontanet J., Herranz L.E., Ramla-kan A., Naicker L., “Modelling of HTR confinement behaviour dur-ing accidents involving breach of the helium pressure boundary”, Science and Technology of Nuclear Installations, 2009.

• Girault N., Bosland L., Dickinson S., Funke F., Güntay S., Herranz L.E., Powers D., “LWR sever acci-dent simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry”, Nuclear Engineering and Design 243, 371-392, 2012.

• Güntay S., Suckow D., Dehbi A., Kapulla R., 2004. ARTIST: intro-duction and first results. Nucle-ar Engineering and Design, 231, pp.109-120.

• Herranz L.E., López C., Velasco F.J.S., Aerosol Retention near the Tube Breach during Steam Gener-ator Tube Rupture Sequence”, Nu-clear Technology, vol. 154, 1, 85-94, April 2006.

• Herranz L.E., del Prá C.L., Dehbi A., Major Challenges to Model Aerosol Retention near a Tube Breach during SGTR Sequences, Nuclear Technology, 158, 83-93, April 2007.

• Herranz L.E., García M., Otero B., Iodine chemistry effects on source term assessments: A MELCOR 1.8.6. YT of a PWR severe accident sequence, ICAPP’09, Tokyo (Ja-pan), 2009.

• Herranz L.E., Ball J., Auvinen A., Bottomley D., Dehbi A., Housiadas C., Piluso P., Layly V., Parozzi F., Reeks M., Progress in understand-

ing key aerosol issures, Progress in Nuclear Energy 52, 120-127, 2010a.

• Herranz L.E., Clément B., In-con-tainment source term : Key insights gained from a comparison between the PHEBUS-FP programme and the US-NRC NUREG-1465 revised source term, Progress in Nuclear Energy 52, 481-486, 2010b.

• Herranz L.E., Vallejo I., Khvostov G., Sercombe J., Zhou G., “As-sessment of fuel rod performance codes under ramp scenarios inves-tigated within the SCIP project”, Nuclear Engineering and Design 241, 815-825, 2011.

• Herranz L.E., López C., ARI3SG: Aerosol retention in the secondary side of a steam generator: Model essentials, verification and corre-lation, Nuclear Engineering and Design 248, 2012a.

• Herranz L.E., García M., Kissane M.P., “In-containment source term in accident conditions in sodi-um-cooled fast reactors”, Progress in Nuclear Energy 54, 138-149, 2012b.

• Herranz L.E., López C., “MEL-COR predictability of spent fuel degradation under complete loss of coolant in storage pools”, SFP Project Seminar, OECD Confer-ence Centrum, Paris (France) 22-23 October 2013.

• Kljenak I., Dapper M., Dienstbier J., Herranz L.E., Koch M.K., Fon-tanet J., “Thermal-hydraulic and aerosol containment phenomena modelling in ASTEC severe ac-cident computer code“, Nuclear Engineering and Design 240 (2010) 656–667.

• López C., Herranz L.E., ARI3SG: Aerosol retention in the secondary side of a steam generator: Model validation and uncertainty analy-sis, Nuclear Engineering and De-sign 248, 282-292, 2012.

• Sagrado I., Vallejo I., Herranz L.E., Analysis of experimental RIA sce-narios: CIEMAT contribution to the OECD RIA international Pro-ject, DFN/SN-02/OP-13, April 2013.

• Sánchez F.J., López C., Herranz L.E., Aerosol Retention in the Vi-cinity of a Breach in a Tube Bundle: An Experimental Investigation, Aerosol Science and Technology, 44, 349-361, 2010.

• Van Dorsselaere J-P, et al., The European Research on Severe Ac-cidents in Generation-II and -III Nuclear Power Plants, Science and Technology of Nuclear Installa-tions, 2012.



The group of thermal-hydraulic studies (GET) of the Technical University of Catalonia (UPC)

is currently participating in different international projects in the field of dynamic analysis of nuclear systems behaviour under accidental scenarios. Such initiatives could be classified in two groups: those developed in the framework of a common effort of di-fferent Spanish universities and those build up by the group itself with other sponsorship. In the former group one can find projects like CAMP (under the leadership of the NRC), OECD-RO-SA project dealing with experi-ments performed at the LSTF facility (JAEA-Japan) and OECD-PKL2 pro-ject dealing with experiments perfor-med at the PKL facility (Areva-Ger-many). In the latter group one can find three projects: BEMUSE, UAM and PREMIUM. Both groups of projects are strongly connected with a general strategy established and sponsored by the Spanish Nuclear Safety Coun-cil (CSN). Since the former group is well known by the Spanish nuclear community, the purpose of this text is to describe the participation of UPC-GET in the latter group of projects. UPC-GET members are the authors of the work done in these projects. The names of the researchers are the fo-llowing: E. de Alfonso, C. Arenas, L. Batet, J. Freixa, E. Mas de les Valls, V. Martínez, M. Pérez, R. Pericas, C. Pre-tel and F. Reventós.

BEMUSE is the first of these pro-jects and it has been already comple-ted. BEMUSE stands for Best Estimate Methods for Uncertainty and Sensi-tivity Evaluation. It has been a pro-gramme promoted by the working Group on Accident Management and Analysis (GAMA) and endorsed by the Committee on the Safety of Nu-clear Installations (CSNI). BEMUSE represents an important step towards a reliable application of high-quali-ty best-estimate and uncertainty and sensitivity evaluation methods. The application of these methods to a Lar-ge-Break Loss of Coolant Accident (LB-LOCA) constitutes the main acti-vity of the programme, structured into two main stages:• Step 1: Best-estimate and uncertain-

ty and sensitivity evaluations of the LOFT L2-5 test. This step includes Phases II and III (A. De Crécy et al. 2008). LOFT is the only integral test facility with a nuclear core where thermal-hydraulic safety experi-ments have been performed.

• Step 2: Best-estimate and uncer-tainty and sensitivity evaluations of a nuclear power plant. This steps includes Phases IV (M.Pérez et al. 2010) and V (M.Pérez et al. 2011).A presentation of the uncertainty

methodologies to be used by the par-ticipants (Phase I) was included in the first step. The final phase (Phase VI) consisted of the synthesis conclusions and recommendations.

UPC-GET participated in all the phases of the activity being also the coordinator of phases IV and V (de-voted to the exercise related to the nuclear power plant). The team took advantage of the project and managed to come to a common understanding with all the participants on the general aspects involved in the different steps of the calculating exercises. In para-llel with its participation in BEMUSE, UPC managed to develop the so-called UPC-CSN methodology of Best Esti-mate Plus Uncertainty (BEPU) eva-luation, which is a statistical method based on Wilks’ theory with some spe-cific features related to the validation of the basic plant nodalization and also to the reduction of the number of input uncertain parameters. Figu-re 1 shows UPC’s prediction of peak cladding temperature (PCT) for lar-ge break LOCA comparative exercise along with its upper and lower bands.

UAM is the second project. UAM stands for Uncertainty in Analy-sis Modelling. The objective of this project is to conduct an OECD ben-chmark for uncertainty analysis in best-estimate coupled code calcula-tions for design, operation, and safe-ty analysis of LWRs. The proposed technical approach is to establish a

benchmark for uncertainty analysis in best-estimate modelling and coupled multi-physics and multi-scale LWR analysis, using as bases a series of well defined problems with complete sets of input specifications and reference experimental data. The full chain of uncertainty propagation from basic data, engineering uncertainties, across different scales (multi-scale), and phy-sics phenomena (multi-physics) are tested on a number of benchmark exercises for which experimental data are available and for which the power plant details have been released.

Several steps or exercises, each of which can contribute to the total un-certainty of the final coupled system calculation, are prepared by coordi-nators. Participants have to identify relevant aspects of each step and pro-pagate the uncertainties in an integral system simulation for which high qua-lity plant experimental data exist.

The main scope covers uncertainty analysis in best estimate modelling for design and operation of LWRs, inclu-ding methods that are used for safety evaluations.

UPC-GET is participating in selec-ted phases of this project (C. Arenas et al. 2013). The team is gaining ex-perience in the selected steps of the calculating exercises, bearing in mind its own specific goal of establishing a neutron-kinetics-thermal-hydraulic coupled model for a Spanish Nuclear Power Plant having the capability of being used for Best Estimate Plus Un-certainty (BEPU) evaluation in the li-censing context.

The third project is PREMIUM, Post BEMUSE REflood Models Input Uncertainty Methods, a project endor-

GROUP OF ThERMALhydRAULIC STUdIES (GET) OF TEChNICAL UNIVERSITy OF CATALONIA (UPC)

Figure 1. Base case and uncertainty upper and lower bands results obtained at the UPC for a large break LOCA in the BEMUSE project.


UNIVERSIdAd POLITéCNICA dE MAdRId (UPM)

Figure 2. Prediction of the quench front propagation in the FEBA experiment of the UPC group (PREMIUM project).

sed by the OECD/NEA/CSNI/WGAMA group. The objective of PREMIUM is to progress on the issue of the quantification of the uncertainty of the physical models in system thermal-hy-draulic codes, by considering a particular case: the physical models involved in the predic-tion of core reflooding. The final goals of the project are: the as-sessment of advanced methods and tools used for event/acci-dent analysis and the review of current analytical tools as well as risk assessment approaches regarding their applicability to safety assessments of new de-signs, and their further develop-ment and validation.

PREMIUM is structured in 5 phases to deal with the quantification of the uncertainties for the influential physical models in the reflooding. The participants will:• Determine the uncertain parame-

ters of their code associated with these physical models (Phase 1 and 2).

• Quantify the uncertainties of the-se parameters using FEBA/SEFLEX experimental result or own reflood experiment (Phases 3)

• Confirm the found uncertainties by uncertainty propagation in the case of the 2-D reflood PERICLES expe-riment. This part will be performed as a blind analysis. (Phases 4 and 5)UPC-GET intends to participate in

all the phases of the activity being also the coordinator of Phase 1. The team will try to take advantage of the project to develop a methodology to quantify the uncertainties for different physical models. Figure 2 shows UPC’s prediction of Quench Front in FEBA experiment compared with the asso-ciated experimental data.

REFERENCES• A. de Crécy, P. Bazin, H. Glaeser, T.

Skorek, J. Joucla, P. Probst, K. Fujioka,

B.D. Chung, D.Y. Oh, M. Kyncl, R. Pernica, J. Macek, R. Meca, R. Macian, F. D’Auria, A. Petruzzi, L. Batet, M. Perez, F. Reventos “Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE pro-gramme”, Nuclear Engineering and Design 2008. • Perez M, Reventos F, Batet L, Pericas R, Toth I, Bazin P, de Crecy A, Germain P, Borisov S, Glaeser H, Skorek T, Joucla J, Probst P, Ui A, Chung B, Oh DY, Kyncl M, Pernica R, Manera A, D’Auria F, Petruzzi A, Del Nevo A. “Main results of phase IV BEMUSE project: Simulation of LBLOCA in an NPP”, Science and Technology of Nuclear Ins-

tallations 2010.• M.Perez, F.Reventos, L.Batet, A.

Guba, I.Tóth, T.Mieusset, P.Bazin, A.de Crécy, S.Borisov, T.Skorek, H.Glaeser, J.Joucla, P.Probst, A.Ui, B.D.Chung, D.Y.Oh, R.Pernica, M.Ky-ncl, J.Macek, A.Manera, J.Freixa, A.Petruzzi, F.D’Auria, A.Del Nevo “Uncertainty and Sensitivity Analy-sis of a LBLOCA in a PWR Nuclear Power Plant: Results of the Phase V of the BEMUSE programme”, Nu-clear Engineering and Design 2011

• C. Arenas, R. Bratton, F. Reventos and K. Ivanov “Uncertainty Analy-sis of Light Water Reactor Fuel La-ttices” Science and Technology of Nuclear Installations 2013.

The UPM participates in seve-ral international projects related with Nuclear Safety which can

be split in two groups: • those which have been funded by

EURATOM, involving four pro-jects in nuclear safety (NURESAFE, SARGEN-IV, ESFR, ESNII+) and in three projects about education in nuclear safety (ENEN-III, TRAS-NUSAFE, NUSHARE), and

• those corresponding to other in-ternational projects which have been funded in Spain by CSN and UNESA: CAMP, NEA/OECD PKL, NEA/OECD ROSA, NEA/OECD ROSA-2, NEA/OECD SM2A, IDPSA network. The following description is mainly

focused on the first group because there are other projects like CAMP, NEA/OECD PKL or NEA/OECD ROSA which are well-known or are described with more detail by other groups inside this paper.

NURESAFE

The NURESAFE project addresses sa-fety of light water reactors which will represent the major part of fleets in the world along the whole 21st century. The first objective of NURESAFE is to deliver to European stakeholders a reliable software capacity usable for safety analysis needs and to develop a high level of expertise in the proper use of the most recent simulation tools. Nuclear reactor simulation tools are of course already widely used for this purpose but more accurate and predic-tive software including uncertainty as-sessment must allow quantifying the margins toward feared phenomena occurring during an accident and they must be able to model innovative and more complex design features.

This software capacity will be based on the NURESIM simulation platform created during FP6 NURESIM project and developed during FP7 NURISP project which achieved its goal by ma-

king available an integrated set of sof-tware at the state of the art. The objec-tives under the work-program are to develop practical applications usable for safety analysis or operation and de-sign and to expand the use of the NU-RESIM platform. Therefore, the NURE-SAFE project concentrates its activities on some safety relevant “situation tar-gets”. The main outcome of NURESA-FE will be the delivery of multiphysics and fully integrated applications.

The platform will achieve the cou-pling neutronics, thermal-hydraulics, and fuel performance codes, at va-rious physical and time scales. In par-ticular it should incorporate new mo-dels addressing recent findings from safety research as well as demands from the current plant operation, as new fuel designs, higher resolution in energy, time and space. Full time dependent solutions of stochastic and deterministic 3D neutron transport should be developed to model hetero-geneous core configurations.



In the NURESIM Platform is inclu-ded the participation of twenty two European organizations ASCOMP, CEA, CHALMERS, EDF, HZDR, KIT/FZK, GRS, IMPERIAL COLLEGE, IN-RNE, IRSN, JSI, KFKI, KTH, LUT, NRI, PSI, TUDELFT, UCL, KIT/UNIKA, UPISA, UPM, VTT. The UPM is invol-ved in the multiphysics and multiscale simulation capacity as a main objec-tive in the nuclear reactor modelling nowadays, joint with the high perfor-mance computing power, in order to take advantage of the advanced hard-ware features as parallel computation. The multiphysics simulation capability may be composed of individual phy-sics capabilities and common support services separately, and a software tool capable of integrating the separate pie-ces.

CP-ESFR: COLLAbORATIVE PROJECT ON EUROPEAN SOdIUM FAST REACTOR

Besides the Generation IV Internatio-nal Forum (GIF), which focuses on the medium-long term (> 2040), the inter-national nuclear community are defi-ning a new framework to fit with the short - medium term. Among them, the European Technology Platform on Sus-tainable Nuclear Energy (SNE-TP) and its European Strategic Research Agenda (SRA) propose a vision for the short, me-dium and long-term where the sodium technology as a reactor coolant plays a key role.

The roadmap for a European Innova-tive Sodium cooled Fast Reactor defines its specific R&D strategic objectives for a fourth generation European Sodium cooled Fast Reactor (ESFR). The road-map addresses the needs for research and development, as well as for tech-nology demonstration. The project ES-FR follows this action identifying, orga-nizing and implementing a significant part of the needed R&D effort.

The UPM contribution has been a Doctoral dissertation for development and verification of the European NURESIM platform for pin-by-pin and nodal coupled NK-TH simulation codes with applica-tion for the ESFR core physics and safety analysis. The analy-sis of the impact of the minor actinides concentrations on the transients results. The UPM has collaborated also in the analysis of the simulation results obtai-ned with different TH codes for representative design basis ac-cidents.

SARGEN-IV PROJECT

The ESNII was launched in November 2010 to anticipate the development a

fleet of fast reactors with closed cycle. Three fast neutron technologies have been selected:• the Sodium cooled Fast Reactor with

the ASTRID prototype.• the Lead cooled Fast Reactor with the

ALFRED demonstrator which will be preceded by a pilot plan MYRRHA.

• the Gas cooled Fast Reactor with the ALLEGRO demonstrator.With the objective of future assess-

ment of these advanced reactor con-cepts, the SARGEN_IV Project is in-tended to gather safety experts from recognized European Technical Safe-ty Organizations from Designers and Vendors as well as from Research Insti-tutes and Universities to:• develop and provide a tentative com-

monly agreed methodology for the safety assessment,

• identify open issues in the safety area, mainly addressing and focu-sing on assessment relevant ones,

• detect and underline new fields for R&D in the safety area

• provide a roadmap and preliminary deployment plan for safety-related R&D, including cost estimation.With the aim of preparing the future

assessment of these advanced reactor concepts, the SARGEN_IV Project is intended to gather safety experts from 22 partners from 12 Member States in order to: • identify the critical safety features of

the selected Generation IV concepts, relying on the outcomes from exis-ting projects from the 7th Framework Programme (FP7),

• develop and provide a tentative com-monly agreed methodology for the safety assessment, relying on the out-comes of the investigations carried out within international organiza-tions (such as IAEA, WENRA, AEN), on national practices presently in use and on practices proposed within other European Framework Pro-grams projects,

• identify open issues in the safety area, mainly addressing and focusing on assessment relevant ones, detect and underline new fields for R&D in the sa-fety area (addressing methodological, theoretical and experimental issues, as well) in order to provide a roadmap and preliminary deployment plan for the fast reactor safety-related R&D.

IdPSA NETwORk

UPM, together with CSN and In-dizen Technologies, participates in IDPSA network which stands for In-tegrated Deterministic/Probabilistic Safety Analysis. IDPSA is considered as a complementary to PSA and DSA approaches intended to help in: Resol-ving time dependent interactions be-tween physical phenomena, equipment failures, control logic, operator actions in analysis of complex scenarios; Identi-fication and characterization of a-prio-ri unknown vulnerable scenarios, or “sleeping threats”; Consistent treatment of different sources of uncertainties; Reduction of reliance on expert judg-ment and assumptions about interde-pendencies; Potential reduction of the cost of safety analysis due to larger in-volvement of computers in what they can do better: multi-parameter, combi-natorial exploration of the plant scena-rios space.

IDPSA network provides a platform for: regular exchange of information and experience between IDPSA re-search and developers, and Potential users: PSA/DSA practitioners in Utili-ties, Vendors and Regulators.

ESNII+

The European Sustainable Industrial Initiative ESNII+ project (2013-2017) aims to define strategic orientations for the Horizon 2020 period, with a vision to 2050. To achieve the objectives of ESNII, the project will coordinate and support the preparatory phase of legal,

administrative, financial and governance structuration, and ensure the review of the diffe-rent advanced reactor solutions.

The UPM is contributing in two different tasks within the project. The first task is the as-sessment of core safety parame-ters for high fidelity transient safety analysis of the ASTRID sodium-cooled fast reactor. The second task is related with the evaluation of the sensitivi-ty coefficients with respect to nuclear data, and the uncer-tainties on the reactivity coeffi-

cients using TSUNAMI-3D/SCALE6.1 module of the ALFRED lead cooled re-actor.

Figure 3. Boron dilution transient power peak calculation (MW) in 3D with CO-BAYA3/FLICA coupled codes by UPM in the NURESIM Platform.


EdUCATION ANd TRAINING IN NUCLEAR SAFETy EUROPEAN PROJECTS: ENEN-III, NUShARE, TRASNUSAFE

The ENEN-III project (2009-2012) co-vered the structuring, organization, coordination and implementation of training schemes in cooperation with local, national and international tra-ining organizations, to provide trai-ning to professionals active in nuclear organizations or their contractors and subcontractors. The training schemes provide a portfolio of courses, training sessions, seminars and workshops for continuous learning, for upgrading knowledge and developing skills in Nu-clear Engineering.

The UPM has collaborated in the de-velopment of the training scheme for non-nuclear engineers and personnel of nuclear facilities, contractors and subcontractors. Two UPM alumni we-re also trained in the scheme for de-sign challenges of GEN III plants.

TRASNUSAFE (2010-2014), a Project supported by the European Commis-sion, aims at designing, developing and validating two training schemes on nu-clear safety culture for professionals operating at a high level of managerial responsibilities in nuclear installations. One of the training schemes is rela-ted to the nuclear industry, while the other is related to the other installa-tions making use of ionizing radiation

based technology, mainly the medical sector. Both training schemes will have a common basis reflecting the challenging approach to risk management, followed by sector-specific specialized modules. The final product will consist in a packa-ge of five training modules for managers of both industrial and medical sectors, ready for use after validation through pilot sessions.

The objective of NUSHARE (2013-2016) is to develop and implement training and informing activities with the aim to share and grow, across EU Member States, the safety culture in nuclear installations. Se-curity aspects (in particular, proliferation resistance and physical protection) will also be treated.

SENUbIO. GROUP OF TEChNICAL UNIVERSITy OF VALENCIA

The research group SENUBIO (Nuclear Safety and Ionizing Ra-diations Bio-engineering) forms

part of the Environmental, Radiophy-sics and Industrial Safety Institute of the Universitat Politècnica de València (UPV). This group has strong relations with several universities and institu-tions abroad the world. We mention, Università di Pisa, particularly with the Professor D’Auria in the area of coupled codes, University of Dresden, particularly with the Professor Hen-ning in the area of Boiling Water Re-actor (BWR) instabilities, Technische Universität München, particularly with the Professor Macián in the area of un-certainties, Karlsruhe Institute of Tech-nology, particularly with the Professor Sánchez in the area of coupled codes, Università de Milano, particularly with the Professor Zio in the area of Re-liability analysis, University of Chal-mers, particularly with the professors Demàziere and Pazsit in the area of neutron noise analysis, with the insti-tute INSTN of the CEA of France, par-ticularly with the professor Eric Royer in the area of coupled codes, with the Paul Scherer Institute and the nuclear plant KKL of Switzerland in the area of BWR instabilities, and with Univer-sity KTH in the area of uncertainties. Regarding universities and institutions of America, the research group has re-lations with the Federal Universities of Rio de Janeiro and Minas Gerais in the area of coupled codes, with Pennsylva-nia State University, particularly with the Professors Ivanov and Avramova in the areas of coupled codes and un-certainties, with the University of Ur-bana-Campaign, particularly with the professors Kozlowsky and Udinn in the area of BWR instabilities, with the University of North Carolina at Raylei-gh, particularly with the professor Az-my in the area of transport equations,

and with the Tennessee University and Oak Ridge National Laboratory in the area of BWR instabilities.

Furthermore, we must mention that the research group has relations wi-th the companies, AREVA, SIEMENS, WESTHINGHOUSE, EDF, STUD-VISK and the Spanish companies IBERDROLA, TECNATOM… The re-search areas are neutronic and ther-mal-hydraulic coupled codes, BWR ins-tabilities, neutron noise fluctuations and signal analysis.

Furthermore, SENUBIO Research group has participated in the USNRC CAMP program (Code Applications and Maintenance Program), which repre-sents the international framework for verification and validation of NRC Ther-mal Hydraulic codes.

In this frame, SENUBIO has actively worked in the international projects OECD/NEA ROSA and OECD/NEA ROSA II, simulating different acciden-tal scenarios using the thermal hydrau-lic code TRACE. ROSA (Rig of Safety Analysis) comprises a series of experi-ments performed in the Large Scale Test Facility (LSTF) of the Japan Atomic Energy Agency (JAEA). The OECD/NEA ROSA project has investigated is-sues in thermal-hydraulics analyses re-levant to water reactor safety, focusing on the verification of models and simu-lation methods for complex phenomena that can occur during reactor transients.

The SENUBIO group has focused efforts in the simulation of the following experiments:• Test 6.1: pressure vessel upper head

Small Break Loss-Of-Coolant Acci-dent (SBLOCA) under the assumption of total failure of HPI System.

• Test 6.2: pressure vessel lower plenum SBLOCA under the assumption of to-tal failure of HPI system.

• Test 3.1: cold leg SBLOCA under the as-sumption of total failure of HPI system.

• Test 3.2: high-power natural circulation due to failure of scram during a Loss-Of-Feed Water (LOFW) transient un-der the assumption of total failure of HPI system, but an actuation of Auxiliary Feed Water (AFW).

• Test 5: condensation-induced water hammer tests.Regarding to OECD/NEA ROSA II

project, we have used the TRACE code to simulate the following experiments:• Test 2: 17% cold leg intermediate

LOCA.• Test 3: 1.5% hot leg SBLOCA with an

assumption of total failure of HPI system, under two different pressure conditions as a counterpart to PKL-2 Project test. Major test objectives were to clarify responses of core exit thermocouples (CETs) vs. fuel rod surface temperature at both of hi-gh-and low-pressure conditions co-rresponding to the pressure range of LSTF and PKL facilities.

• Test 5: thermal-hydraulic responses after a PWR Steam Generator Tube Rupture (SGTR) induced by Main Steam Line Break (MSLB).Main results and conclusions of the-

se works are summarized in different NUREG-IA reports (4 corresponding to ROSA project and 3 corresponding to ROSA II project).

Organizers of ROSA projects, OECD/NEA and the operating agent (JAEA) have encouraged the participation of all involved groups by means of different meetings (at least two per year) and a final Workshop “Joint PKL2-ROSA2 workshop on analytical activities rela-ted to PKL/OECD and ROSA/OECD projects” held in Paris (2012). Discus-sions and information exchange have been fruitful and allowed us to improve our knowledge of thermal hydraulic phenomena involved in important tran-sients in Nuclear Safety.


On-Site Field ServicesM. Rodríguez Aycart, E. Bobo, L. Pascual, A. Merino, I. Martínez Gozalo, J. T. Ruiz, M. Soto & S. Vilanova

THE ENUSA STRATEGY FOR THE ACCESS TO INTERNATIONAL NUCLEAR FUEL MARKETS

Why “going abroad”

The reasons behind the progressive globalization of the ENUSA opera-tions can be found in the behaviour of its reference markets. As it be-came clear in the ‘80s that the Span-ish market was not going to grow in the years ahead, the company decided to break into the European markets. As a result ENUSA is now exporting products and services to France, Belgium and Sweden.

Now, given the reduction trend of the European PWR and BWR fuel markets (see Figure 1) ENUSA is looking abroad again to expand its business.

From the maximum in years 2009-2010 the market is expected to reduce its size in approximately 20% due to the early shutdown of 23 reactors within the period 2007-2023 and only two new connections to the grid. The major part is obvi-ously due to the German phaseout although other countries will see some of its reactors shutdown too.

Another factor which contributes to the internationalization strategy is the high level of competition in the European fuel market. Currently there are five nuclear fuel factories in operation in Europe under the control of three different fuel ven-dors. Total installed capacity largely exceeds the current fuel needs.

The new markets being less ma-ture than the European, offer clear advantages such as a significant demand for new technology and growing market size. In addition,

ENUSA: MARIANO RODRÍGUEZ AYCARTHead of ENUSA’s Commercial and Business Development Unit.EMILIO BOBO PÉREZArea of Business Development. Internationalization process in the Business Development and Fuel Technology Management.ENWESA: LUIS PASCUAL RODRÍGUEZCommercial Director.IBERDROLA INGENIERÍA Y CONSTRUCCIÓN:ALEJANDRO MERINO TEILLETas Director of the New Nuclear Plants Department.IGNACIO MARTÍNEZ GOZALOChief Project Manager in the new plants and large projects section of New Nuclear Plants Department.LAINSA: JOSE TOMáS RUIZEurope & Asia Business Director.MARCELO SOTO TOMáSProduction Manager in LAINSA and Technical Director in Gertisa SAU.WESTINGHOUSE: SERGI VILANOVA CUADRADO Field Service Engineer/Project Manager.

The Spanish nuclear industry has extensive experience in the development of services for nuclear power plants.

The moratorium on new projects in the decade of the 1980s led these nuclear industry companies to find and enter new markets.

The quality of their services, along with the long experience gained in the sup-port of the Spanish plants, has enabled a significant number of companies to win relevant contracts in competition with leading corporations around the world.

European countries are an important market. The first experiments to support the operation in Central and Eastern Europe are being extended with work in neighboring countries. Meanwhile, Latin America is a nearby market for reasons of language and historical proximity, which is also present in the industry. It emphasizes the participation of Spanish companies in projects in countries of the Asia-Pacific region.

This article describes the experiences of four Spanish-owned companies and of the services division of Westinghouse in Spain.

ENUSA

these markets offer positive projec-tions of nuclear development for the next decades. Overall, the new capacity up to 2030 in the most op-timistic scenario is expected to ex-ceed 350 GWe (Figure 2).

Segmentation

It is possible to make different segmen-tations attending to criteria such as ge-ographical expansion areas, products and customers. A short review of each of these is presented below.

Figure 1: Evolution of the PWR and BWR European nuclear fuel market.(Source: ENUSA).



Chinese CGN and CNNC, which not only operate their own reactors but produce uranium concentrates, pro-vide enrichment and conversion ser-vices, manufacture fuel assemblies, etc. These companies may search for virtually any kind of product in the market.

Finally, the accumulated experience at ENUSA in the design and operation of advanced inspection equipment paves the way to a direct relationship with the fuel manufacturers. Together with its partners, ENUSA can pro-vide technological solutions for fuel manufacturing plants by adapting the technology developed at Juzbado plant to the specific requirements of other fuel vendors.

Association: best approach for mid-sized companies

The size, distance and complexity of the international markets make it advisable to search for the appropri-ate partners either in the country of origin or in the foreign market.

ENUSA has already adopted both practices. As a founding member of the Spanish Nuclear Group for Co-operation (SNGC) it is one of the four Spanish companies which have associated to join forces to enter into foreign markets. The SNGC provide marketing and coordination ser-vices to its members and performs a high level scrutiny of the most promising business opportunities.

The other approach ENUSA is fol-lowing is the association with local companies in the export market. This is being done with the assis-tance of a sales agent who knows the specifics of the country and has di-rect contact with the local company. Once the company has been iden-tified the usual approach is to sign a Memorandum of Understanding (MoU) to serve as a contractual um-brella for the relationship.

So far ENUSA has entered into a number of MoU with different Asian and South American compa-nies (see Figure 3) and representa-tion agreements in Brazil, Argentina and China.

Conclusions

Internationalization implies a cul-tural change in the organization. A significant effort on development of technology, quality improvement and efficiency must be undertaken throughout the company. ENUSA is working on these areas by im-plementing a more efficient organ-

Geographic segmentationFigure 2 shows how the new ca-pacity is distributed worldwide. Weakness of the European market can be clearly identified when com-pared to the trends in regions such as Asia-Pacific. The expected added capacity in this region alone may ex-ceed 200 GWe up to year 2030.

Other regions are newcomers to nuclear energy. Middle East coun-tries are shifting from a traditional oil-based electricity generation to cleaner, carbon dioxide-free produc-tion systems based on nuclear and renewable electricity.

It is also relevant to focus on the South American market. Both Ar-gentina and Brazil are building new reactors and there is a long-term investment plan for new nuclear capacity. These countries are de-veloping their own industry which eventually will cover the entire fuel cycle. However some of its historic partners, in particular the German companies, are no longer in the nu-clear business, what represents an opportunity for ENUSA.

Product segmentationIn the last years ENUSA has evolved from a pure fuel manufacturer to a more integrated fuel services ven-dor. Fuel services now include spent fuel, on site services have grown to add additional inspection capabil-ities and a new equipment design and manufacturing business is be-ing created.

Nuclear fuel is the reference prod-uct of ENUSA and its credentials in the international markets. However the fuel market is a regional market where the fuel is produced close to the point of consumption. This lim-its the potential expansion of pure

fuel vendors although it also ex-plains the ENUSA success in the Eu-ropean market, well communicated and geographically small compared to other regions.

Commercialization of fuel in-spection equipment offers many advantages. First, there is a limited competition in this field and second, normally it is not subject to politi-cal or technological barriers as the nuclear materials. ENUSA is work-ing very actively in developing its technology together with its partner TECNATOM. As a result of these ef-forts new fuel inspection equipment has been sold to China and Brazil and there is a significant potential for new sales in other markets.

Finally a third pillar is constitut-ed by the spent fuel services. The Spanish Interim Centralized Stor-age Facility (“ATC”) project and the maturity of the Spanish nuclear sec-tor has brought this topic to a first line of sight. ENUSA has decided to cooperate with ENRESA, ENSA and other Spanish companies to devel-op its own capabilities in this field, mainly linked to the dry storage of nuclear fuel.

Customer segmentationThe addition of new products and services to the ENUSA portfolio pro-gressively broadens the perspective of potential customers. Traditionally the main customer has always been the utility/operator of a nuclear power plant and being the nucle-ar fuel a key supply for the power plant, the relation operator-fuel vendor will maintain its strategic nature either in the traditional or new markets.

In the new international markets however one can now find vertically integrated conglomerates such as the

Figure 2: New global capacity in an optimistic scenario. (Source: ENUSA).


ization, boosting its continuous im-provement program and reinforcing its investment on R&D, which cur-rently ranges between 6% and 10% of the total annual sales.

Internationalization also means growing business and this results in the need for additional human, technological and financial resourc-es. This can only be achieved with a clear strategic determination and a strong institutional backing from the Administration. In the case of state-owned enterprises a third factor must be considered, which is the support of the SEPI holding, ENUSA’s main shareholder, to in-ternationalization initiatives. These conditions and the new reality of globalization present the best sce-nario for ENUSA to pursue its inter-national development and reinforce its relevant place in the nuclear in-dustry worldwide. Figure 3: ENUSA international cooperation agreements.

ENWESA

ENWESA IN THE INTERNATIONAL MARKET

ENWESA develops its international activity of nuclear services both in Europe (France, Finland, Sweden, Belgium, etc.) and America (Mexico and Brazil basically).

The international presence of EN-WESA started right after its foun-dation in 1985, although it has been strengthened during the last years due to the important effort ENWE-SA has made in the French nuclear market.

In the middle of the last decade, ENWESA defined as strategic the French nuclear market for several reasons: its geographical proximity, its high potential and specially, the very good feedback received from the power plant managers to EN-WESA’s services portfolio. From that moment, ENWESA set out an am-bitious plan that basically consisted in obtaining the required qualifica-tions, training people specifically in French working methodology, and opening a well located branch office that brought ENWESA closer to the plants where services are performed.

At present, ENWESA has an im-portant activity of maintenance ser-vices in French nuclear power plants property of EDF. These works of in-spection and maintenance of equip-ment, valves and condensers are carried out both during the refueling outages and during the operation of the plants.

Part of the international activity of ENWESA is developed in collab-oration with its shareholders EQUI-POS NUCLEARES and WESTING-HOUSE. Both companies have a significant international activity and ENWESA collaborates with them contributing with its capacity and providing highly qualified personnel in nuclear services.

With EQUIPOS NUCLEARES, ENWESA participates the construc-tion, mechanical erection and main-tenance in nuclear plants of Finland and Sweden.

With WESTINGHOUSE, ENWE-SA participates in the inspection and maintenance of nuclear components in Slovenia, France, Belgium, etc.

Additionally, ENWESA cooper-ates with other important firms, like ENUSA, IBERDROLA INGENIER-IA or AREVA, in activities related to nuclear fuel, reactor vessel, main coolant pumps, and so on.

Some of the main references of works performed by ENWESA out of Spain are:• EDF: Maintenance of equipment

and valves in Blayais, Tricastin,



Fessenheim, Golfech, Civaux NPPs (France).

• EDF: Condenser retubing in St. Alban I (France).

• ORTEC Group: Maintenance of valves in Cruas NPP (France).

• ENSA: Manufacturing and instal-lation of AMS Neutron Shielding and installation of SG Pressure Equalization Ceiling in Olkiluoto 3 NPP (Finland).

• ENSA: Installation works and repairs in steam generators in Ringhals NPP (Sweden).

• ENSA: Collaboration in devel-opment phases for installation of vacuum vessel of ITER Project.

• WESTINGHOUSE: Maintenance works in cooling reactor pumps, reactor vessel opening and clo-sure and equipment maintenance in Blayais and Gravelines NPPs (France), and Tihange and Döel NPPs (Belgium).

• ENUSA: Fuel inspection, and electro-erosion works in fuel top nozzles in Belgian nuclear plants.

• IBERDROLA INGENIERIA: Me-chanical and QA supervision in erection works of condensers and MSRs in Bohunice NPP (Slovakia) and Laguna Verde NPP (Mexico).

• UDDCOMB ENGINEERING (AREVA Group): Orbital welding works in Oskarshamn NPP (Swe-den).

• AREVA: Valves maintenance in Sizewell NPP (United Kingdom).

• AREVA: Several works related to cooling reactor pumps, steam generators, reactor vessel and fuel handling in Angra NPP (Brazil).Besides, ENWESA participates as

a founding member of Cluster of the Nuclear Industry in Cantabria (Spain), whose main objectives are reinforcing the nuclear industry in Cantabria, increasing the competi-

tiveness and business opportunities of its founding companies, promot-ing the professional training and the creation of qualified employment. This Cluster is clearly international-ly focused, with objectives like the participation in several phases of the “International Thermonuclear Experimental Reactor” (ITER) pro-ject, that is being developed in Ca-darache (France).

It is worth to point out that hold-ing an international activity in the nuclear market in the way ENWESA has done throughout these year in-volves an important factor of knowl-edge to our company and specially to our people, who pervade with different working methods, improv-ing their professional qualification and enriching their technical back-ground, which finally results in a better training to perform our ser-vices in the Spanish nuclear plants.

IBERDROLA INGENIERíA Y CONSTRUCCIóN

DEVELOPMENT OF LARGE INTERNATIONAL CONSTRUCTION AND SERVICE PROJECTS IN NUCLEAR PLANTS. RELEVANT EXPERIENCE OF IBERDROLA INGENIERIA Y CONSTRUCIóN

Summary

IBERDROLA INGENIERÍA Y CONS-TRUCCIÓN (hereinafter IEC) has developed a significant number of large projects in several nuclear plants worldwide. Some of these plants are under operation, while others are under construction. Now-adays, IEC is actively participating in the design and construction of some safety and non safety class systems of Flamanville 3, for EDF, and has successfully closed the project for the refurbishment of Laguna Verde 1&2 turbine islands in Mexico, with a budget above 600 M USD. Howev-er, these projects cannot be understood without taking a look to the back-ground of its internation-al activities in the field of nuclear plants engi-neering and construction services.

The beginning: BRAZIL

International develop-ment of nuclear service and construction pro-jects of IEC started in 1998 with the award of the outage service con-

tract of Angra 1 in Brazil. This first international service contract, with duration of 5 years had limited scope involving management and services activities, although, it served as a scenario to show IEC capabilities to Brazilian customer, utility Electro-nuclear, supposing undoubtedly an important milestone for the award of the next contract in Angra I, for the replacement of the two steam gener-ators by new ones.

The replacement of the steam gen-erators contract was awarded in 2006. This large EPC contract involved an international consortium headed by IEC, involving Westinghouse, and Brazilian construction company Odebtretch. The successful integra-tion of the partners drove to achieve foreseen outage schedule 2008. The scope involved Reactor Coolant Sys-

tem analysis, pipe cut and welding, auxiliary work and the opening of a large hollow in the containment, by using wire rob cutting of the pre-stressed concrete wall and band saw-ing for the steel liner to extract old steam generators and introduce the new ones. In addition, a high accu-racy rigging work was developed for the exchange work with the required precision and safety, while minimiz-ing the interferences with large safety class structures located in the vicinity, as for example large safety systems water storage tanks.

SLOVAKIA, a continuation and a sample of technology and cultural adaptation

In parallel to the expansion of the company in the Americas, several projects were awarded in Europe by Slovak company Slovenska Elek-trarne.

First project was awarded in 2006, con-sisting in the design, supply and on site supervision of the as-sembly of 2 condens-ers to Bohunice nu-clear stations V1 and V2. The novelty of this project was custom-er requirement to on site assembly of con-denser bundles, while these are commonly supplied already as-sembled for its instal-

Design and Execution of Rigging Maneuver for extraction of old steam generator, Angra 1.

lation by customer. Condenser was designed to achieve outstanding efficiency to ensure adequate plant performance at demanding condi-tions of 9% expected power uprate of the plant. Design project involved was also focused in ensuring the re-quired accuracy for the alignment and assembly in Bohunice work-shop to comply with assembly and installation schedules. Of the out-most importance was the IEC supply chain for the components of the con-denser, with specific mention to the local supplies, and the superb work

Extraction Part 2. Design versus reality.

Scheme of Modifications developed in Laguna Verde Units 1 and 2. (not included off gas and turbine ventilation system upgrade).

Laguna Verde Unit 2 Condenser Installation sequence using Modularization scheme of construction (from top left to the right upto lowest right picture).

Detail of Open Top Installation of TG31 condenser bundles. Notice accurate constructability design.

Rigging for new MSR Bohunice.developed by supervision person-nel, which played a relevant work to ensure the constructability of the bundles.

Required thermal performance was complied in excess by the new bundles in front of a third party.

A new project was awarded to replace old Soviet design vertical Moisture Steam Reheaters by new ones of high efficiency design. Two important challenges should be un-derlined for this project. First one is that new equipment should be inte-grated in a previous design, coming from the former days of Soviet Un-ion. Secondly, all installation works, not only supervision, was under the responsibility of IEC, which involved the utilization of local Supply Chain at its maximum extent. Contract was awarded to IEC in 2008, being a re-markable success in both aspects. To remark (1) the outstanding com-pliance of outages schedule, being of the outmost importance the con-structability analysis, which mini-mized interferences and maximize usage of existing turbine cranes, and (2) the exceed of contractual perfor-mance guarantees.

MEXICO, LAGUNA VERDE, largest nuclear project developed by an Spanish company outside Spain

Laguna Verde is a GE BWR-5 station located in the Gulf of Mexico, near Veracruz.

In February 2007 the contract for the complete refurbishment of La-guna Verde Unit 1 &2 turbine island was awarded to IEC, with a budget




above 600 M USD, after a long and demanding bidding process. The goals of the project were moderniza-tion and increase of capacity to adapt turbine island to the new expected conditions at new reactor power level of 120%, and to upgrade turbine is-land for new life extended conditions of 60 years.

Complete information may be found in reference [1].

The project was developed in a scheme based in two outages per unit,

between 2008 and 2010, and involved the complete supply, refurbishment and upgrade for both units of tur-bine generator and auxiliary systems, condensers, feedwater heaters, con-densate pumps, booster pumps, new turbine crane, main trafos, new isolat-ed bus and main switch gear, turbine island ventilation system, with new variable frequency fans to adapt to the demanding environmental condi-tions, offgas system, etc.

FLAMANVILLE 3: the future

Electricite de France (EDF) in 2006 began construction of a new EPR nu-clear reactor in Flamanville central. IEC has been involved for five years in five EPC projects in the construc-tion of the EPR in both the nuclear island and conventional island in the pumping station. Scope of projects involved the design, supply and ons-ite installation of safety class 2 and 3 heat exchangers, and safety and non safety class equipment for the water intake and water treatment.

These projects represent a chal-lenge from the technical point of view because of the high require-ments applicable to the project by the return of EDF operator’s experience and compliance with the new regu-lations arising from the realization of ultimate nuclear plant in France. Additionally, the state of the sup-ply chain after several years with-out building new plants, and the requirement in some of the projects using European standards, customer not accepting American legislation, assumed an additional challenge.

Additional information about these projects may be found in reference [2)].

References

[1]. Spanish Society Magazine, November 2011. Monograph. Alejandro Merino, Jose Luis García- Serrano, Leticia Ruiz, Juan Jose González, Miguel Ángel Gabaldón, Ignacio Prieto.

[2]. Spanish Society Magazine, November 2011. “Iberdrola Engineering and Construction Projects in the Flamanville 3 EPR”. Javier Zornoza, Henri Dumas, José Luis Sesma, Begoña Cubián, José Ignacio Díaz

Picture 7. Installation of several Flamanville Safety Class HX (Open Top and Non Open Top).

Picture 8. Circulation Water Channel Construction. Flamanville 3.

LAINSA

LMQ. AN EFFICIENT METHOD IN ORDER TO RECOVER THE PERFORMANCE OF THE MSRS. A SATISFACTORY EXPERIENCE

Inspections on moisture separa-tor reheaters in the French Nuclear Power Plant has shown evidence of significant clogging due to de-posits of magnetite inside tube bundle whose presence could dam-age equipment and harm produc-tivity. We have developed a proce-dure that consists of a mechanical pre-cleaning of all tubes of the MSR in order to unblock them, followed

by chemical cleaning where mag-netite is dissolved and flushed out of the tube bundle.

The undesirable phenomenon of erosion-corrosion produced in the steam pipes, puts in circulation sig-nificant amounts of iron, which are accumulated, in the form of mag-netite, valves and above all within the pipes of the MSRs and other heat exchangers and on the outside of the tubes bundle of the Steam generator (secondary side).

MSRs Inspections made in French Nuclear Power Plants, induced by

Interior of MSR pipe with magnetite de-posits.

MSR tube bundles in workshop for the LMQ process homologation.

Chemical cleaning schematic.

a decline of the equipment perfor-mance determined that MSRs of Fes-senheim and Bugey Nuclear Power Plants are subject to the build-up of magnetite deposits, resulting from steam eroding the tube system. As deposits build up on the inner surfac-es of the tubes, they impede flow, and increase the pressure drop between inlet and outlet of the MSR. In some cases, the pressure drop amount has been found to be near the maximum design criterion. This effect could re-sult in equipment damage and loss of plant productivity.

We present the alternative of changing the MSR or proceed with a regular cleaning. An economic analysis and time savings induce the second process carrying out.

With this project we developed a method to remove magnetite and oxide deposits from the inner tubes of the MSR in order to recover a passage diameter and an exchange surface equivalent to the original and to prevent loss of plant produc-tivity. This removal should be done in a safe way for the base metal of

the bundle tube, without producing the chemical pitting of the tubes, which would encourage new cycles of erosion-corrosion.

LMQ system of LAINSA

The method basically comprises a first step of mechanical pre-clean-ing by running high pressure water, then introducing a rotary air operat-ed tube cleaner through the tubes of the MSR to unblock the tubes without damaging them. The last step of me-chanical pre-cleaning is a final rinse with high pressure water to eliminate all the residues resulting from me-chanical cleaning and to facilitate the next step of chemical cleaning.

The second step refers to a chem-ical cleaning at low temperature (around 65°C) by using different combination of acids, preferably or-ganic ones (citric acid, ascorbic acid, formic acid), and at low concentra-tion, in order to dissolve the deposits from the inner side of the tubes.

The reaction of dissolution of mag-netite by citric acid (C6H8O7 = AH3)

is based on the following equation:Fe3O4 + 4AH2

- → 2Fe(III) – A + Fe(II) - A- + 4H2O+A3- [1]AH2

- and A3- are chemical species resulting from citric acid (AH3), but the following acid-base reactions:AH3 → AH2

- + H+ , pKa1 = 3.15AH2

- → AH2- + H+ , pKa2 = 4.77

AH2- → A3

- + H+ , pKa3 = 6.40The chemical cleaning operation

also includes the steps of passiva-tion by introducing a passivating agent to create a thin oxide layer on the metallic surfaces to prevent pos-terior corrosion. A final rinsing step at alkaline pH is then carried out to eliminate all the passivation res-idues and to leave the MSR in good operational condition.

Procedure description

B e for e s t a r t i ng me c h a n ic a l pre-cleaning, the MSR is sealed off temporarily with pipe end and pneu-matic plugs, in order to isolate the system.

The first step of the process con-sists of checking for leaks by filling the system with water to a certain pressure.

The second step is mechanical pre-cleaning. Each tube is cleaned with a medium-pressure water jet (100-200 bars) from an electrical hy-drodynamic unit (GHDE). This oper-ation also enables creation of a map of clogged tubes.

The next step of the mechanical pre-cleaning process consists of us-ing a rotary air-operated tube clean-er made of a flexible shaft, and a cleaning tool mounted to the tip of the flexible shaft. A final rinse with high-pressure water (400-600 bars) is carried out using the electrical hy-drodynamic unit.

In the third step of the process, after a leak check (at 30°C), chemical cleaning with a recirculated aque-ous cleaning solution (acid phase) is introduced into the system.

The cleaning solution used to dis-solve the magnetite layers contains

Sealing tool of the MSR water box.



citric acid, formic acid, a corrosion inhibitor and other chemicals. In or-der to improve the cleaning efficien-cy, the cleaning solution is heated to 65°C. This is done by an electrical heat exchanger connected in parallel with the chemical cleaning system.

During the chemical cleaning process, analytical controls are car-ried out periodically (at least each hour) to follow the following pa-rameters:• Temperature• Acidity• ph• Ferric iron concentration

MSR and chemical impulsion area.

LMQ Work Area. Equipment supply area and wastes TK’s.

• Total iron concentration• Inhibitor efficiency

Chemical parameter evolution gmph during the acid phase

The end of the acid phase is de-termined by the criterion of total iron concentration <14 g/L and by the stability of four measurements of total iron concentration.

The final step of chemical cleaning is passivation, which is also carried out with recirculation. The aim is to prevent corrosion of the tubes’ me-tallic surfaces by creating a thin ox-ide layer which protects the surfaces.

During the passivation process,

analytical controls are carried out periodically (at least each hour) to monitor the following parameters:• pH• Temperature• Ferric iron concentration• Total iron concentration• REDOX potential

Three hours later, the solution is drained out of the MSR and the sys-tem is rinsed with alkaline solution.

Results

The results obtained during the various MSR cleaning (14) cam-paigns allowed the validation of the elimination of magnetite deposits. On sample coupons placed in the interior of the top of the MSR tube bundle, the loss of thickness caused by the cleaning process averaged about 10 µm. The load after clean-ing (a measurement of delta P after restarting the unit) was comparable to new equipment.

Conclusions

EDF completed a follow-up of the fouling of the MSR by measuring the pressure delta (∆P). We noticed that the plugging of the bundle be-gins to be significant from a thresh-old of ∆P of 2.5 bars; the maximum ∆P to avoid generation of plastic dis-tortion, and thus MSR damage, is 3.4 bars. It can take four to six years to go from ∆P of 2.7 bars to 3.4 bars.

According to the maintenance strategy envisaged by EDF, when a MSR crosses the threshold of ∆P > 2.5 bar, a cleaning operation is scheduled for the most convenient shutdown less than six years away.

This process has been retained in EDF’s MSR maintenance strategy.

WESTINGHOUSE

WESTINGHOUSE OPERATIONS SPAIN THE YOUNG EXPERIENCE

Westinghouse Operations Spain is increasing its capabilities around the world

Our operations in Spain are mainly located in Hospitalet del Infant (Tar-ragona) supported by a team located in Madrid. Our crews are able to help our customers around the world in some of the most important activities in the power plants.

Currently, our personnel has been giving technical advice and man-power in the fields of I&C, Cranes, Training, Reactor Vessel Head, Fuel activities, Steam Generators, Pumps

and Motors. And this support is in-creasing every project thanks to our dedicated employees. We are proud to have in our facilities a mix of ex-perience and vitality that allows us to achieve the goals of each project. We still have original plant start-up en-gineers in our crew as well as newly hired people able to provide a fresh perspective and new ideas in our group (and nuclear sector).

As a worldwide company our spe-cialist are demanded to support nu-clear needs in of qualified personnel. Below are some of the projects we have been involved with during the past years outside our local area.

We are supporting customers in

South Africa, France and Great Britain performing the maintenance and out-age support to fuel handling equip-ment. Our specialists are trained in help you in Instrumentation System as well as Mechanical systems to get the success of the outage. We are cur-rently working on a refurbishment of an auxiliary bridge crane in a highly contaminated area of a decommis-sioning facility in Great Britain.

We are increasing each day our col-laboration with a Slovenian facility to be one of its principal partners, this collaboration started with a RCP motor swap and other related activ-ities. Currently, this collaboration is increasing with new projects, our cus-

Ask at [email protected]


tomer wants to improve his facility trying to make it an example of nu-clear safety culture, this is the reason we are designing a RTD bypass elim-ination for the reactor head, and in the creation of a isolated bunker for

equipment similar to another which is currently build in a Swiss NPP.

We are always trying to meet or exceed our customer needs, especially when these needs are not expected. We know the importance to be in the plant as fast as possible and we try to be in the plant before 24 hours of any urgent issue as we did for the sup-port complete hydraulic pump com-plete disassembly during a non pro-grammed outage in Switzerland. This emergency support helps us to gain future contract of new parts and long duration material supply contract.

Some activities are rarely per-formed during the life of a power plant and require specialist to per-form the work. It is our goal to have these specialists and train young peo-ple in these rare activities as we did in a Belgian facility modifying some fuel pins or the design of an OSPS for the RCPs in a Swedish NPP.

But not only in the non-routine jobs are needed specialist, during the normal maintenance activities of the outage is necessary that all work order for the correct function of the plant. This is the reason our French colleagues request our support in Reactor Head activities during the maintenance of the plant.

No country is too far for us, we have supported fuel activities in Brazil, and RCP frequently support activities in USA. Our goal is to help our customer with their activities and to grow and learn with them.

Westinghouse Operations Spain as part of Westinghouse group is working everyday for increasing the reliability of the Nuclear Power Plants and their auxiliary systems. Like our customers, we want to con-tinue being a green and safe com-pany to improve the quality of life around the world.

Swapping a RCP motor at Krško NNP.

Nuclear España

In OCTOBER edition of

A comprehensive presentation of all activities, products, services and companies involved in the world of energy.It also includes a guide to all masters in nuclear matter taught in Spain.

Reserve your spaceFREE REGISTRATION

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2013



Co-operation in the development of a policy and strategy for the management of spent nuclear fuel (including provisions for its safe interim storage) and radioactive waste in MexicoP. Zuloaga, M. Molina, J. Bárcena, E. Salas, M. Sánchez, H. Codée & J. Deckers

The European Commission decided in 2010 to finance a project for providing technical support for the definition and establishment of a national policy and strategy for radioactive waste management in Mexico. The Project was in the framework of the Nuclear Safety Co-operation Instrument (NSCI), a European mechanism which finances measures to support a higher level of nuclear safety, radiation protection and the application of efficient and effective safeguards of nuclear materials in third countries. Eventually, the Project was awarded to a Consortium made up by four Spanish companies, ENRESA, Empresarios Agrupa-dos Internacional SA, Iberdrola Ingeniería SAU, Westinghouse Spain SAU, and two foreign ones, COVRA NV and Belgoprocess NV. Both ENRESA and COVRA are waste management agencies, the first responsible of these activities in Spain, the second one in the Netherlands. ENRESA acts as the leader of the Consortium.

The Project started early in 2012 and will last until March 2015. All along this period, the Mexican system for spent fuel and radioactive waste management will be scrutinized and proposals made for its upgrading according to the best international and European standards of safety and performance. A Policy and Strategy document will be proposed, as well as significant improvements for the different institutional layers, practices and elements of the Mexican system.

A total of 40 specialists are involved in the project of which 30 are Spaniards.

PROJECT OBJECTIVES. RW AND SF MANAGEMENT IN MEXICO. A POLICY AND STRATEGY FOR THE MEXICAN SYSTEM

The overall objective of the project is to provide support to the Mexican government in its efforts to ensure responsible, sound and economically efficient management of spent nucle-ar fuel and all radioactive waste gen-erated at Mexican NPPs and other nuclear and radioactive installations. This will be achieved through the following specific objectives:1. Support the development of a

comprehensive National Policy Plan;

2. Support the development of a Strategy to implement this Na-tional Policy Plan, including draft legislation and institutional frame-work, and

3. Develop the Strategy at the level of the largest single waste generator to improve the management of the spent nuclear fuel and radioactive waste generated at Laguna Verde

NPP, in compliance with the Na-tional Policy Plan.The Mexican nuclear sector is

made up of two electricity-produc-ing nuclear reactors, 817 MWe each in the Laguna Verde Nuclear Power Plant (CNLV) in the State of Verac-ruz, a nuclear research centre, the In-stituto Nacional de Investigaciones Nucleares (ININ), which has a TRI-GA research reactor in Ocoyoacac in the State of Mexico, and approxi-mately 600 institutional producers or users of different applications out of the nuclear fuel cycle sector. The an-nual generation of radioactive waste is close to 300 m3, 90% of this quanti-ty corresponding to the CNLV. Most irradiated nuclear fuel comes from operations of the two thermonuclear reactors of the CNLV.

The main powers of regulation and enforcement of nuclear, radi-ological and physical safety and safeguards correspond to the Gov-ernment through the Secretary of En-ergy (SENER) that is responsible for

Pablo ZuloagaPh.D. in Physics Engineering and Industrial Engineer. He has worked in NPP Design and Commissioning and has worked for ENRESA since 1986 as El Cabril project manager, responsible for Projects and Construction, LLW and HLW Department. At present, he is the Engineering Director of ENRESA.

Mariano MolinaIndustrial Engineer, Polytechnic University of Madrid. He has more than 20 years of experience in RW Management. Presently, he is the Head of the Department of International Relations of ENRESA.

J. bárcenaIndustrial Engineer, University Carlos III of Madrid. Since 2007, he works for Empresarios Agrupados, being responsible for several projects on RW management and decommissioning of nuclear and radioactive facilities.

eVa SalaS Degree in Physics, University of Zaragoza. She has 13 years of experience in radioactive waste management. Currently, she works as Senior Engineer in the Waste Management and Decommissioning Unit of Iberdrola Ingeniería SAU.

MoiSéS SáncheZ Industrial Engineer, by the Polytechnic University of Madrid and Master in Business Administration by the IE Business School of Madrid. He has more than 26 years of experience in Decommissioning & Dismantling. Presently, he is W&D&D Product Manager in Westinghouse Spain.

h. codéePh. D. Chemistry, State University Leyden and Reactor Institute Delft. He has been working in SF and RW management since 1982. Managing director of COVRA NV, the Dutch Radioactive Waste Management Agency since 1995. He has a background in chemistry and radiation protection and has been working in the area of radioactive waste management for more than 30 years. Since 1995 he is managing director of COVRA N.V.

J. deckerSIndustrial Engineer, Master in Environmental Sanitation. He has been developing his career in radioactive waste management for more than 30 years. Presently, he is the Technical Commercial Manager of Belgoprocess NV.



Figure 1. Main facilities for Spent Fuel and Radioactive Waste Management in Mexico.

Figure 2. Institutional Framework in Mexico

decisions to be taken on some of the issues that need urgently to be addressed, specifically with regard to the used nuclear fuel storage ca-pacities of the Laguna Verde Pow-er Plant;

• To lay down the starting points for developing a management strate-gy that enables medium and long-term technical actions to be deter-mined and focused;

• To review, adapt and strengthen the existing allocation of responsi-bilities among the bodies involved in spent fuel and waste manage-ment to achieve the overall objec-tive of ensuring safety during the entire period in which waste is harmful;

• To pave the way for the definition and establishment of a funding system for management of radioac-tive waste and spent nuclear fuel;

• To update existing legislation gov-erning spent fuel and radioactive waste to align their mandates to those established in international practices and legislation.The Project is organized around

three main Tasks. Task 1 is to carry out a full assessment of the current situation of radioactive waste and spent fuel management in the coun-try, to make a comparative evalua-tion with the most advanced OECD countries in this area and finally to propose a document containing a po-tential policy for México. Task 2 scru-tinizes the main items that impact on the amelioration of the Mexican system, this comprising the potential establishment of radioactive waste management agency, the implemen-tation of a new funding scheme, or the full development of management facilities and practices from waste production to its eventual disposal. The outcome of this Task is a docu-ment proposing a long-term national strategy for the country. Task 2 will be mainly fed by the results of Task 3 which specifically addresses the op-timization of radioactive waste and spent fuel management in CNLV.

AN IMPROVED INSTITUTIONAL FRAMEWORk IN MEXICO FOR SF AND RW MANAGEMENT

A relevant activity which flows from the considerations above is the de-sign of an institutional framework that could better respond to the re-quirements of the proposed policy. The main international legal texts, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and the Council Directive 2011/70/Euratom

the storage, transportation and “de-posit” of any nuclear fuel and radio-active waste produced in the country, regardless of their origin. SENER has issued delegations for discharging these duties onto CNLV and ININ, the first for managing its own waste, the latter for its own waste and those coming from institutional produc-ers. The functions of regulating and supervising nuclear safety and secu-rity are carried out by the Comisión Nacional de Seguridad Nuclear y Salvaguardas (CNSNS), the Mexican nuclear safety regulatory body.

Throughout this time, the Mex-ican system has worked well and has provided an appreciable level of radiological safety and physical se-curity for the country’s population,

both during normal operating cir-cumstances as well as at other times when there have been incidents and accidents that have required organ-ised and efficient actions. The aims of the current system have been reason-ably achieved in most of the cases.

The point that the Project tackles is the implementation of a policy and a strategy for considering the long term aspects of safety and security, which have not yet been addressed. With this respect, the Project propos-es to give priority to the following issues:• To lay down the starting points for

the immediate development of a short-term management strategy which completes the existing man-agement framework and allows


of 19 July 2011 establishing a Commu-nity framework for the responsible and safe management of spent fuel and ra-dioactive waste strongly insist on this point. An appropriate institutional framework is a fundamental requi-site to achieve the long-term safety and security objectives unanimously accepted by the international com-munity.

The Consortium has recommend-ed the reinforcement of the country’s institutional framework by means of a better and wider allocation of responsibilities among the bodies legally involved. The main findings and recommendations in this area are the following: • The Federal Government should

promote legislation to empow-er the State to guarantee the safe management of any SF and RW; the Government should establish a financial scheme to cope with the long term management neces-

sities. An appropriate, stable flow of funds is a fundamental require-ment for the successful implemen-tation of any strategy;

• The independence of the CNSNS must be fully achieved, and its role in the visibility and acceptance of the proposed solutions improved;

• The primary responsibility of li-cense holders should be legally stated and reinforced; particularly, they must provide for and main-tain adequate financial resources to fulfill their long-term obliga-tions;

• The responsibilities for long-term management of spent fuel and radioactive waste must rest on a dedicated or specialized imple-menting body, or National Radio-active Waste Management Agency, which will be in charge of turning into practice the long-term man-agement objectives as stated in the National Policy and Strategy.

MAXIMIZING THE RW AND SF MANAGEMENT SYSTEM OTHER THAN THE INSTITUTIONAL FRAMEWORk

As mentioned before, CNLV and ININ currently manage the waste under their responsibility following internationally accepted practices, but independently from each other. The establishment of a national strat-egy is highly convenient for getting a full optimization of the minimiza-tion and management of radioactive waste in the country. This is the main goal of Task 2 of the Project.

Up to now, the main conclusions of the Consortium are focused in the maximization of existing capabilities and the implementation of addition-al mechanisms to improve systems and processes involved in the man-agement activities. Among the main recommendations are the following:• The National Inventory of radio-

active waste and spent fuel should be officially established and kept updated both at the quantitative and radiological level. The new inventory should also consider potential additions in the Mexican nuclear fleet as well as the waste arising from future decommission-ing of nuclear plants.

• The optimization of the sorting-out processes and the implementation of treatment models in line with the features and characteristics of the radioactive waste should fa-cilitate minimizing its generation, thus optimizing the amount of waste packages and disposal units after their conditioning.

• The unification of the requisites and techniques for the physical, chemical and radiological charac-terization of the wastes will help in selecting the most appropri-ate conditioning processes. As a consequence, the total amount of waste will be minimized and the resulting products will have the

Figure 3. Scope of the Project.

Figure 4. TRIGA reactor at ININ. Figure 5. Treatment facilities at ININ.



required quality for its storage or disposal.

• The best envisaged op-tion for very low level waste and low and in-termediate level waste is their disposition in a single centralized facili-ty, following the existing models of near surface repositories. The facility should also host treat-ment and conditioning installations and interim storage capacity. Until this facility comes into operation, the existing capacities for institutional producers at ININ should be maintained.

• A Centralized Storage Facility (CSF) or Independent Spent Fuel Installations (ISFISs) at the NPPs seems to be the best solution for the long-term storage of spent fuel depending on the size of the future nuclear power fleet. Pres-ently, there is just the need of the scheduled ISFI at CNLV. A CSF is the best solution if further NPPs would come on line.

• The Mexican Waste Management Agency must set generic criteria and methodologies to make easier the future common management, according to the waste inventory, the new treatment processes and disposal facility.

• The Mexican policy and regula-tions must strive for promoting the return of disused sealed sourc-es to the manufacturer. It is also required to improve the facilities for the storage of and treatment of orphan sources and specially to set up the strategy for its final disposal.

OPTIMIZING THE RW AND SF MANAGEMENT SYSTEM IN LAGUNA VERDE NPP

The specific assessment of CNLV, prior to proposing a detailed im-provement of its practices, begun by collating and scrutinizing all avail-able information as to better under-stand the current situation concern-ing radioactive waste and spent fuel management. There was also the intention of identifying the most rel-evant aspects for subsequent tasks. A comprehensive questionnaire was used for this purpose.

Following the response of the NPP, a report was issued which depicted management practices in CNLV and compared them with those interna-tionally advised. The main conclu-sion was that radioactive waste man-

agement in the plant is safely carried out and in line with international standards. Further analysis detected some areas which needed to be clari-fied and potentially improved. A first presentation in a Project’s Workshop, late in 2012, contributed to better un-derstand CNLV conditions and to ask for additional information. A fur-ther visit to the NPP in May 2013 also helped to get a more accurate knowl-edge of the spent fuel and radioac-tive waste management installations. It also provided a direct contact with the staff responsible of these activi-ties and better consideration of their interests and expectations.

Taking all the above mentioned information as a basis, Task 3 of the Project is currently oriented to specif-ically assess the main management aspects, among of which there are the following:• Different waste streams and best

minimization practices;• Best technologies for waste treat-

ment and conditioning;• Interim storage and waste accept-

ance criteria to comply with the requirements of long-term storage as defined in Task 2;

• Spent fuel storage.Again, the assessment of these

items will be focused on detecting pending issues or areas to be im-

proved according to the Consortium experience and its applicability in Mexico.

For each of the areas listed above, a report will be drafted provid-ing the assessment of al-ternative options as well as the best recommenda-tions or improvements, all to be discussed and agreed with the Benefi-ciary.

Finally, all the different recommenda-

tions will be integrated in a docu-ment to become the proposal of a Strategy for the optimization of the spent fuel and radioactive waste management in CNLV. The Strategy will be aligned with the best interna-tional practices, costs optimization and the National Policy, as defined in Task 1. CNLV’s Strategy is destined to be the basis for a wider National Strategy which, taking into account all radioactive waste produced in Mexico, will become the main result of the Project.

STATUS OF THE PROJECT. MAIN FINDINGS AND CONCLUSIONS

The assistance to the Mexican Au-thorities for improving their prac-tices on spent fuel and radioactive waste management will continue until the first quarter of 2015. By the end of 2013, the analysis of the main elements and components of the Mexican system will be completed thus allowing the drafting of a com-prehensive Strategy to be presented and discussed with the main stake-holders by the end of 2014. The new Mexican Government, in the mean-while, has started the preparations for internally discussing the issuance of a Policy. To this end, SENER has asked the cooperation of the Con-sortium. This latter is presently com-pleting some reports which address potential keystones of the future

Figure 6. Visit to Laguna Verde NPP, May 2013.

Figure 7. Spanish Disposal Concept for LILW.

Mexican institutional framework: full defi nition of a potential national agency for radioactive waste man-agement, a new funding system, strategic guidelines for disposal of low and intermediate level waste and interim storage of spent fuel.

Overall, the co-operation with the Mexican authorities is proving to be a good example of how existing know-how in some European coun-tries could be transferred to third countries as to form a sound basis for the achievement of the best inter-nationally accepted standards. With this respect, the long experiences of countries like Spain, Belgium and the Netherlands in radioactive waste management is a high valuable asset, whose added value comes from the diversity of nuclear systems involved and the existence of sound manage-ment systems in each of them. It is to be highlighted that two national agencies (ENRESA and COVRA)

with a long tradition of helping the European Commission in shaping the EU practices are being to bring this European acquis to Mexico.

The Spanish industry is playing a signifi cant role in the Project as three Spanish engineering compa-nies (Empresarios Agrupados Inter-nacional SA, Iberdrola Ingeniería y Cosntrucción SAU y Westinghouse Spain SAU) are working together, covering every point in the improve-ment of the future technological ca-pabilities in Mexico, as well as in the defi nition of the strategic directions to be followed. A key aspect of their contribution is the large stock of knowledge accumulated during the development of the main facilities and installations of the Spanish ra-dioactive waste and spent fuel man-agement system (Disposal center of El Cabril, C.N. José Cabrera decom-missioning, disposal concepts for SF and HLW, etc.).

ACkNOWLEDGMENTS

The authors wish to express their gratitude to the Development & Co-operation Directorate-Gener-al of the European Commission responsible for the coordination and follow-up of the activities involved in the project “Co-op-eration in the development of a policy and strategy for the man-agement of spent nuclear fuel (including provisions for its safe interim storage) and radioactive waste in Mexico”. Its support and understanding are of piv-otal importance for the under-taking of it. It is also necessary to highlight the relevant role being played by the Mexican au-thorities, especially SENER and ININ, whose continuous co-op-eration has become crucial for the achievement of the Project’s objectives.


Reus Tradeshow and Convention CenterREUS, TARRAGONA

Meeting of energy

professionals


The evolution of nuclear energy. Opportunities for the industryM.ª T. Domínguez

EVOLUTION OF THE TECHNOLOGY IN NUCLEAR POWER PLANTS IN OPERATION

The evolution of the technology of the reactors in operation is driven by the objective of maximizing nu-clear assets to adjust their costs to operate in more competitive scenar-ios. Two areas are the major contrib-utors here: the extension of the op-erational cycle up to 60 or 80 years, and the power uprating and in-crease in availability of the reactors by increasing their energy output.

Initiated in the US, the strategy of renewing licenses for long-term oper-ation up to 60 years was well devel-oped and supported by the US Nu-clear Regulatory Commission (NRC) and the nuclear industry as a whole. The Electric Power Research Institute Long-Term Operation Program (EPRI - LTOP) got underway in 2009 is now a large, collaborative research effort reaching across multiple countries and entities, among them, Spain.

Spanish industry has closely fol-lowed and developed capabilities in all the research activities associ-ated with the long term operation

defined by EPRI in preparation of their application to our nuclear re-actors. Primary system degradation, advanced welding processes, reactor surveillance, concrete aging man-agement, cable aging management, diagnostics and integrated life-cycle management are some of the areas of research in this program. In this con-text, it is relevant the coordi-nation effort made by UNESA providing access to the most relevant EPRI documentation for the applicability analysis to the Spanish NPPs.

In addition to this investiga-tion and research oriented at a 60-year operation horizon, the DOE has recently launched the Light Water Reactor Sustaina-bility Program to develop the scientific basis for extending nuclear power plant operation life beyond 60 years.

The LWRS Program is di-vided into four research path-ways: Materials Ageing and Degradation, Advanced Instru-mentation, Information, and Control Systems Technologies,

MARIA TERESA DOMíNGUEZAdvanced Projects Director, Empresarios Agrupados.Member of the EU Advisory Group on Energy (AGE).Member of the VHTR GEN IV Project Management Board.

Areas of Evolution in Operating Reactors

At the turn of the XXI century, the world energy context underwent a significant change due mainly to the increases in the demand for energy in the developing countries, a rise in gas prices and increased government support of clean ener-gies in response to environmental issues. These boundary conditions led rapidly to renewed interest in nuclear energy worldwide. The phrase “a Renaissance in nuclear energy” was included in almost all energy forecasts. Unexpectedly, how-ever, just ten years later the panorama changed once again: unconventional gas appeared as a new energy source, the world financial crisis hampered invest-ment, and the demand for energy fell. This panorama has lowered expectations with regard to the size of the nuclear energy renaissance to a less bouyant but more balanced scenario of nuclear energy deployment that we could now dub as the “evolution of nuclear energy”.

This article describes how fission nuclear energy has continuously been evolv-ing to adjust itself to these changing scenarios and, in particular, how it is being adapted itself to today’s vision of the role of the nuclear energy in the long term. The analysis in this paper focuses on those programs that could bring opportuni-ties for Spanish nuclear industry participation.

Starting with the development programs affecting existing reactors already in operation, the analysis moves on to the new builds of Light Water Reactors (LWR) Generation III+, to then address, in two sections, Research Reactors and finally, the opportunities presented by Generation IV technologies. The development of fusion technology is not covered in this paper.

Risk-Informed Safety Margin Char-acterization and Advanced Light Water Reactor Nuclear Fuels. De-scriptions of each of these pathways follow, together with highlights of recent results. This program will offer opportunities for the Spanish nuclear industry to participate in the near future.


INTERNATIONAL NUCLEAR mARkET

Gen III+ RPV Support Design performed by Empresarios Agrupados.

bility of the use of nuclear energy for energy production. These research reactors, normally located at the universities and research centers, are now being dismantled due to a lack of use for the purpose for which they were built. Nevertheless, there are today strong drivers to deploy research reactors. These drivers are

for supporting evolutionary and advanced reactors development Gen III+ and Gen IV, and to sup-port nuclear energy applications different from electricity produc-tion, mainly for medical applica-tions. The production of isotopes is one of the major applications.

One example of research reactor development in which the Span-ish industry is involved is the Jules Horowitz Reactor (JHR), that will be built and operate in the framework of an international cooperation be-tween several organizations.

With an investment of about 750 million Euros, JHR is expected to start operating in 2016. The reactor is a pool type reactor. The maxi-mum thermal power is 100 MW. This power is dissipated via the primary and the secondary circuit to the external cold source during irradiation; the core, the primary

The second line for maximizing nuclear assets is related to the in-crease of capacity factors and power uprating. In this respect, the effort of the Spanish nuclear industry has been relevant, with very positive re-sults. The 2012 operating results of the Spanish NPPs as a whole, with a load factor of 88.82%, an availability factor of 89.84%, an operation factor of 90.60%, non-programmed una-vailability of 1.33%, and an increase of 6.4% in nuclear energy generation over 2011 all evidence the top-level performance of the Spanish installa-tions in terms of generation.

This level of excellence in the op-eration of reactors reflects the com-mitment of the utilities and is in-dicative of the skills of the Spanish nuclear industry supporting plant operation. This expertise as “opera-tors” is attractive on the internation-al market where new contracting schemes that combine vendors and operators in joint ventures, for ex-ample, the BOT contract model, are being implemented.

EVOLUTION OF TECHNOLOGIES IN THE NEW CONSTRUCTION OF NUCLEAR REACTORS

Construction of the new generation of LWRs known as Gen III+ has be-gun. 36 new reactors in 15 countries are now being built. Russia, China, Korea, India, Europe and United States have programs under which Generation III+ reactors, of vari-ous technologies, mainly PWR and BWR, are under construction. In re-sponse to the increased nuclear en-ergy deployment foreseen at the end of the XX century, vendors began developing evolutionary reactors. Thanks to this effort, the ESBWR GE-Hitachi; ABWR GE-Hitachi; AP-1000 Westinghouse Electric Compa-ny; EPR AREVA; APR-1400 Korea Electric Power Corporation; APWR Mitsubishi Heavy Industries; AES-2006 VVER, Rosatom are examples of the available Gen III+ reactors that will most likely be in operation in the next decade, bringing to the nuclear industry additional exper-tise in licensing new processes, pro-ject organization and construction models, passive system behavior, advanced engineering and CAD de-sign tools, etc.

The participation of the Span-ish nuclear industry in most of the above developments has been and continues to be relevant. Starting with the Spanish Advanced Reactor Programme launched 20 years ago,

Spanish industry is being involved in most of these new built programs, either in design activities, in pro-curement or in EPC contracts for packages.

The participation of Empresari-os Agrupados in the Design Cer-tification of the GEH ESBWR per-forming design activities, licensing reports such as the Design Control Document and Responses to NRC Additional Information Requests; in the technology evaluation of the different reactor technologies for specific site applications; and in the development of engineering design packages supporting EPC contrac-tors for New Build proposals are rel-evant examples of this participation.

EVOLUTION IN THE RESEARCH REACTORS TECHNOLOGY

Apart from the use of the nuclear energy for electricity production, there are several areas of develop-ment supporting the commercial reactors and other applications of nuclear energy. These areas refer to the basic research supporting the technological development of Gen III+ and Gen IV.

In the 1950s, Research Reactors were a tool to demonstrate the via-


circuit and experimental rigs, are completely enclosed in the Reactor Building. The Reactor pool is con-nected to several storage pools and hot cells located in the NAB through a water block. Material investiga-tion, isotope production, spent fuel behavior experiments, hot cell and laboratories development are major missions that the JHR will tackle for the international community.

Spanish industry is providing inkind contribution to the JHR that will be compensated by rights to use the reactor for future research. This work is instrumented through a CEA-CIEMAT agreement. A rele-vant part of the scope of the in-kind contribution of Spanish industry covers the design and manufactur-ing of the three Primary Heat Ex-changers. Empresarios Agrupados is responsible for the design, and ENSA is responsible for the man-ufacturing. Two other companies, Tecnatom and Socoin, are contrib-uting with the experiment simula-tion platform. Similar opportunities could arise in the future.

EVOLUTION OF THE NEXT GENERATIONOF FISSION REACTORS

The GEN IV/GIF initiative, launched by USA in 2000, was the pillar for the consolidation of sever-al initiatives of advanced technolo-gies existing at that time around the world at the laboratory level. GIF has made it possible to join the ef-fort and create an industrial forum capable of selecting the most prom-ising technologies and defining de-ployment strategies. The main driv-ers of these Gen IV reactors are an increase in use of the fission resourc-es (U, Pu, Th, etc.) and optimizing the management of nuclear waste. Europe’s participation in GIF has allowed focusing the EU research

program towards its contribution to the Generation IV reactors.

Sodium-cooled Fast Reactor (SFR), Very High Temperature Re-actor (VHTR), Supercritical Water Cooled Reactor (SWCR), Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR) and Molten Salt Reactor (MSR) are the technologies being considered as Gen IV reac-tors. Over GIF’s 13-year existence, the results of basic research and small-scale experiments have been shared among the members. Now, it is time to build the Demonstra-

tors. The international community is proposing to contribute to this new phase, proposing the construc-tion of several installations. In pre-paring the Horizon 2020 program, Europe is attempting to embark on the construction of prototypes. Three main initiatives, among oth-ers, are being considered in the EU Strategy Energy Technology Plan (SET-Plan): ASTRID (Advanced Sodium Technology Reactor), AL-FRED (Advanced Lead Fast Reac-tor), MYRRHA (Multi-purpose Hy-brid Research Reactor for High-tech Applications).

The most advanced initiatives are the MYRRHA project supported by the Belgium Government and open to collaboration, and ASTRID, sup-ported by the French Government to be built in CEA (France). ASTRID is a 600 MWe reactor with fast spec-trum. Preliminary studies started in 2010, and conceptual design studies are now under way. Construction will start in 2020, and the reactor is expected to be in operation in 2025. The reactor is the result of interna-tional collaboration between Rus-sia, India, USA, Japan, Europe, Ko-rea and China. The Spanish nuclear industry could participate through

JHR - Plant layout and Main Heat exchanger. In-kind contribution by CIEMAT-ENSA-Empresarios Agrupados.

MYRRHA: a consortium participated by Empresarios Agrupados, selected for FEED activities.

EU SET-Plan Strategy.


INTERNATIONAL NUCLEAR mARkET

the EU Framework Program Hori-zon 2014-2020, now in preparation.

MYRRHA is a flexible research re-actor of 100 MWth coupled to an ac-celerator. The linear accelerator will deliver a high density high-energy proton beam of 600 MeV to the LBE (Lead Bismuth) spallation target.

The installation will be built by the Belgium Nuclear Research centre (SCKCEN) in Mol with an estimated budget of 960 million euros. Construction on the facility is expected to begin in 2015, with commissioning by 2023. SCKCEN has recently decided to launch the related Front End Engineering Ac-tivities (FEED). For this purpose, a consortium in which Empresari-os Agrupados is participating has been selected to perform this FEED phase. Civil design, the electrical distribution system, HVAC, fire pro-tection, containment, and the Beryl-lium doping system are part of the activities assigned to Empresarios Agrupados in this project.

CONCLUSIONS

After 50 years of use, nuclear ener-gy has proven its value as an energy source and its possible contribution in all long term scenarios is beyond question. Thanks to its continuous-ly technology evolution, the nuclear energy is mature and innovate.

The nuclear industry has evolved in response to the changing scenari-os, always with a long-term perspec-tive. This article has focused on the recent developments in nuclear ener-gy to be more competitive, to better use nuclear fission resources, and to optimize the management of nuclear waste.

The investment required for this development is shared between governments and industry. As this article states, the nuclear industry is supporting extensive modernization programs of the reactors currently in operation and of the advanced LWR of Gen III+, while the Research and the New Technologies of Gen IV are being supported more by Govern-

mental organizations. As a result of these investments, the nuclear in-dustry now has many opportunities to participate in these developments.

The Spanish nuclear industry has always responded to new challenges and is thus involved in almost all of the international nuclear programs described in this article. Its participa-tion in the life extension programs, power uprating, research reactors, and advanced reactors described in this article are evidence of this in-volvement.

Nevertheless, the level of Spanish participation and investment in these nuclear programs is currently not on a par with our industry’s capabilities and the excellence of the Spanish NPPs in operation. One of the prima-ry goals of the Spanish institutions and nuclear industry should be to increase its involvement. Initiatives similar to the Advanced Reactor Pro-gramme launched 20 years ago upon joint government and industry effort should be convenient.

La Sociedad Nuclear eSpañola convoca un concurso para elegir el logotipo de conmemoración de su 40º aniversario en 2014, que será utilizado en los actos de celebración y en los documentos editados por la SNE durante ese año.

Pueden participar los socios individuales, sus familiares directos y los empleados de los socios colectivos de la SNE.

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INFÓRMATE EN:

y participa con nosotros

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NEWS of the WORLDadVanced nuclear reactor proJects to receiVe usd 3.5 million from doeGeneral Atomics, GE Hi-tachi, Gen4 Energy and Westinghouse will receive 3.5 million US dollars (2.68 million euros) for four nucle-ar research projects that “go beyond the traditional light water design”, the US de-partment for energy said.

The financial support, which will be offered with a 20 percent private cost share, is part of President Barack Obama’s plan for re-ducing pollution from fossil fuel power plants and devel-oping clean energy technol-ogies, announced last week.

The DOE said the projects will address “key technical challenges” to designing, building and operating the next generation of nuclear reactors.

empire state reactorA novel consortium has an-nounced participation in the American funding contest for new small reactor de-signs. Proposing a high-tem-perature helium cooled re-actor, the group features strong support from the state of New York.

Hoping to demonstrate new reactor concepts by 2022, the Department of Energy is running the second stage of a competition for cost-sharing support for new small modular reactor (SMR) development. On offer is ac-cess to up to $226 million, for which a range of compa-nies have placed bids. Bab-cock & Wilcox’s mPower re-actor won the first round and was given access to $79 mil-lion in November 2012.

National Project Manage-ment Corporation (NPMC) is leading the latest bid to be announced. It includes a cluster of regional partners in the state of New York: the

state government itself, the City of Oswego, the Port Au-thority of Oswego, Empire State Development and New York State Energy Research and Development Authority.

Also in the team are the Pebble Bed Modular Re-actor (PBMR) company of South Africa and National Grid, the power grid opera-tor based in the UK but with a US operation counting 3.3 million customers in New York, Massachusetts, and Rhode Island.

Reactor conceptsThe NPMC-led project spec-ifies a gas turbine modu-lar high-temperature reac-tor (GT-MHR) concept as a ‘common nuclear engine’ which could be adapted to three main tasks: generating electricity; supplying heat for industry or production of hydrogen; and a ‘deep burn’ of used nuclear fuel materi-als that would produce heat and power while simplifying waste disposal.

This description match-es the publicised benefits of General Atomics’ GT-MHR, which was developed through the 1980s and 1990s, latterly with part-ners in Japan and Russia where a prototype was once intended to be built. How-ever, the nameplate gener-ating capacity of 165 MWe matches the former PBMR design rather than Gener-al Atomics’ ~280 MWe GT-MHR, and General Atom-ics is not mentioned in the NPMC bid. General Atomics has actually submitted its own bid to the DoE based on a variation of GT-MHR known as the Energy Multi-plier Module.

PBMR’s project in South Africa has been shelved, but the company’s tech-nology has certain parallels with the GT-MHR concept. Both are based on ‘Triso’

fuel particles where a 0.5 mm speck of uranium oxide fuel is contained in several layers of silicon and carbon and embedded in a graph-ite matrix. PBMR’s design has these formed into ten-nis ball-sized pebbles that make up a large core, while GT-MHR has them in hexag-onal prisms that build into a compact core block. Both designs also use helium as coolant, directly driving a turbine-generator set.

In November 2012, the Babcock & Wilcox (B&W) mPower reactor was select-ed as the winner of the first round of funding, receiv-ing access to $79 million to commercially demonstrate the design by 2022. A sec-ond round of funding was announced in March 2013. The DoE anticipates award-ing those funds by mid-Jan-uary 2014. The maximum amount available in each of the first and second rounds is set at $226 million.

Source: 13 August 2013 World Nuclear News

tWo research proJects for larcdB loans 16 Billion rtWo research proJects for large-scale adVanced pWr pass pre-acceptance

Major special research pro-jects have passed pre-ac-ceptance in Shanghai. They are large-scale advanced pressurized water reactor on “AP1000 nuclear island major key design technolo-gy” and “AP1000 nuclear island key equipment de-sign technology research”.

The pre-acceptance group was made up by the acade-mician of Chinese Academy of Engineering, Ye Qizhen, Chief Engineer of China Ma-chinery Industry Federation, Sui Yongbin and more than 20 well-known experts in nuclear power technology.

The group agreed that both of the two issues have achieved their expected ob-jectives and content of the mission statement of con-tract, and completed the required assessment indi-cators. This indicates that China has mastered the technology system for the third-generation internation-al advanced nuclear island design, and has already had its own design capability of AP1000 nuclear island.

The major PWR projects include the AP1000 tech-nology digestion and absorp-tion, CAP 1400 technology research and development, CAP1700 technical pre-re-search, PWR common tech-nology and condition secu-rity. These two topics that have passed the pre-accept-ance belong to the topic of AP1000 technology diges-tion and absorption with 15 sub-topics and 55 special subjects, and 1,700 copies of technical documentation. Now the technology inno-vation achievements have been used on AP1000 fol-low-up project and part of the AP1000 relying project.

Source: http://www.cfhi.com

russian assistance on three continents

Russia is funding a new technology centre in Viet-nam and cooperating with an Argentine university, help-ing develop the skills need-ed for nuclear programs in those countries. Meanwhile, Rosatom claims more than 15,000 jobs could be creat-ed if South Africa proceeds with its nuclear energy ex-pansion plans.

Russia and Vietnam signed an agreement in November 2011 covering the construc-tion of such a centre in Viet-nam. Under the terms of that agreement, the Russian gov-ernment will provide loans


worth $500 million for the centre’s construction.

Feasibility studies and site selection are underway, ac-cording to director of the Vietnam Atomic Energy In-stitute (VinAtom) Tran Chi Thanh. “Work on the pro-ject will probably begin in late 2015, under favoura-ble conditions, and we have proposed building it in the Central Highlands city of Da Lat,” he told the Tuoi Tre newspaper. Once operation-al, the new centre will be used for conducting scien-tific research and developing technologies to support Viet-nam’s planned nuclear pow-er program. A research reac-tor at the new centre will be used for training programs as well as the production of medical isotopes.

Vietnam’s plans for nucle-ar power are well advanced. The country’s Atomic Ener-gy Law came into force in 2009 and intergovernmen-tal agreements in place with Russia and Japan allow for the construction of its first two nuclear power plants, both in Ninh Thuan province. Construction work has yet to begin, although the first Rus-sian-designed unit at Ninh Thuan I is pencilled in to be-gin operation by the end of 2020.

Argentina assistance

A memorandum of coopera-tion on cooperation in nucle-ar education has been signed between the University of Buenos Aires and Rusatom Overseas - the subsidiary of Russia’s Rosatom state nu-clear corporation concerned with exports of nuclear pow-er plants. Russia and Argen-tina have signed many coop-eration agreements in recent years, including one in 2010 which expresses Russian willingness to partner Argen-tina in designing and building plants in Argentina based on Russian VVER pressurized water reactors. In 2011, the two countries signed a mem-orandum on cooperation in the peaceful use of atomic energy that recognises Rosa-

tom as a possible supplier for a fourth Argentinian nuclear power plant.

South African localization

Rosatom is ready to help South Africa with its plans to construct six nuclear power reactors, executive vice-pres-ident of Rusatom Overseas Boris Arseev announced last week.

Speaking at the annual conference of the Nuclear In-dustry Association of South Africa (NIASA) in Port Eliz-abeth, he claimed, “The im-plementation of the South African nuclear generation development program togeth-er with Rosatom would cre-ate 15,000 additional jobs in construction, service and operation of the new units, as well as several thousand jobs in related industries.”


Westinghouse in spain leads a consortium for the Bohunice V1 decommissioning plan

A consortium composed of Westinghouse, Tracte-bel Engineering and Sogin S.p.A has been selected by Jadrová a vyra’ovacia spoloc-nos’ (JAVYS) to develop the licensing documentation to obtain the license for stage 2 of the Bohunice Nuclear Power Plant (NPP) V1 de-commissioning, and pro-vide the necessary engineer-ing to support the licensing documentation. The pro-ject is financed by the Bo-hunice International Decom-missioning Support Fund (BIDSF), administered by the European Bank for Re-construction and Develop-ment (EBRD). The Bohunice V1 NPP, located in western Slovakia, consists of two VVER-440 V-230 nuclear reactors.

A Westinghouse Spanish team is in charge of leading the international consortium to prepare, review or update the licensing documents for obtaining the authoriza-tion for the stage 2 decom-

missioning of Bohunice V1; and to develop the neces-sary analyses, studies and assessments to support the licensing documentation for stage 2 decommissioning of Bohunice V1.

Brazilian office for snptc

China’s State Nuclear Pow-er Technology Corp (SNPTC) has set up its first South American office in Rio de Janeiro, Brazil.

The office was formally in-augurated by Chinese consul general Chen Xiaoling and Shen Weidong, the head of SNPTC’s Brazilian delega-tion, at a ceremony attended by diplomats and represent-atives of Chinese business-es, enterprises and financial institutions. At the ceremo-ny, Chen Xiaoling said that she hoped the office would enrich and enhance the level of bilateral cooperation be-tween the two nations.

China has developed its own indigenous reactor designs taking as a start-ing point the reactors built there by overseas suppli-ers. Two Chinese-designed CNP-300 PWRs are cur-rently under construction at Chashma in Pakistan, and Chen Xiaoling point-ed to the “broad prospects for cooperation” in various fields already enjoyed by those two countries.

SNPTC was set up in 2004 to take charge of technology selection for new plants being bid from overseas, and has exten-sive overseas partnerships, notably with Westinghouse. Together the two compa-nies are working on the construction of four West-inghouse-supplied AP1000 reactors at Haiyang 1 and 2 and Sanmen 1 and 2, the first of a fleet of AP1000 reactors planned for China. Technology transfer to gen-eral contractor SNPTC has formed a major part of the project, and the company is involved in the develop-ment of the CAP1400 reac-

tor with a view to the export market.


latest chinese reactor Vessel installation

The reactor pressure ves-sel has been installed at the first new reactor of the Fang-chenggang nuclear power plant in western China.

Construction started just over three years ago with the laying of the concrete base-mat for the reactor build-ing. Main contractor China Nuclear Power Engineer-ing Corp (CNPEC) reached a new milestone on 27 Au-gust by placing the pressure vessel inside which the unit 1’s reactor core will produce heat for power generation.

Fangchenggang is located near Hongsha village in the Guangxi Autonomous Re-gion, about 45 kilometres from the border with Viet-nam. A total of six reac-tors are planned to operate there. Units 1 and 2 are CPR-1000s, units 3 and 4 are planned to be the evolu-tionary ACPR-1000 develop-ment, and units 5 and 6 are to be AP1000s. All of these are models of large pressur-ized water reactor.



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20 asociación nuclear ascó-vandellos ii 12 central nuclear de cofrentes 39 chepro 46 coapsa 4ªc eMpresarios aGrupados 1 endesa 3ªc ensa 52 enusa 6 Grupo doMinGuis 11 iberdrola inGeniería y construcción 34 inGeniería idoM 26 norca inGeniería 18 rinGo vÁlvulas 45 taMoin 2ªc tecnatoM 57 técnicas servicios inGeniería 2 WestinGhouse

Julio Acumulado Acumulado1.066 MW en el año a origen

Producción bruta MWh 744.971 4.305.641 201.483.907Producción neta MWh 696.929 4.034.160 188.646.670Horas acoplado h 709,8 4.157,5 193.544Factor de carga o utilización % 93,93 76,40 85,89Factor de operación % 95,40 81,73 87,66 Paradas automáticas no programadas 0 0 11Paradas automáticas programadas 0 0 18Paradas no programadas 0 1 29Paradas programadas 1 1 33

Julio Acumulado Acumulado466 MW en el año (*) a origen (*)

Producción bruta MWh 0 0 133.335.074Producción neta MWh 0 0 126.976.805Horas acoplado h 0 0 302.218,01Factor de carga o utilización % 0 0 77,74Factor de operación % 0 0 81,44Paradas automáticas no programadas 0 0 150Paradas automáticas programadas 0 0 9Paradas no programadas 0 0 62Paradas programadas 0 0 59

Junio Acumulado Acumulado1.092 MW en el año a origen

Producción bruta MWh 789.219 5.483.254 225.586.836Producción neta MWh 758.023 5.270.975 217.225.640Horas acoplado h 744 5.087 226.005,53Factor de carga o utilización % 99,14 98,71 86,90Factor de operación % 100 100 89,17 Paradas automáticas no programadas 0 0 96Paradas automáticas programadas 0 0 7Paradas no programadas 0 0 11Paradas programadas 0 0 32

Ascó I Julio Acumulado Acumulado1.032,5 MW en el año a origen

Producción bruta MWh 765.710 5.290.170 213.548.352Producción neta MWh 733.224 5.084.205 204.753.707Horas acoplado h 744 5.087 225.842,28Factor de carga o utilización % 99,68 100,72 82,90Factor de operación % 100 100 85,97Paradas automáticas no programadas 0 0 92Paradas automáticas programadas 0 0 5Paradas no programadas 0 0 19Paradas programadas 0 0 27

Ascó II Julio Acumulado Acumulado1.027,2 MW en el año a origen

Producción bruta MWh 764.380 3.834.370 206.425.360Producción neta MWh 732.681 3.666.695 198.154.750Horas acoplado h 744 3.825,90 216.753,23Factor de carga o utilización % 100,02 73,38 86,33Factor de operación % 100 75,21 89,03 Paradas automáticas no programadas 1 2 60Paradas automáticas programadas 0 0 4Paradas no programadas 0 0 12Paradas programadas 0 1 28

TRILLO IUFG 34,5%, IBERDROLA G. 48%,

HC G. 15,5%, NUCLENOR 2%

NUCLENOR (ENDESA G. 50%, IBERDROLA G. 50%)Sta. Mª DE GAROÑA

ENDESA G. 72%, IBERDROLA G. 28%

Julio Acumulado Acumulado1.087,14 MW en el año a origen

Producción bruta MWh 785.363 4.467.736 191.745.402Producción neta MWh 753.515,20 5.252.731,40 183.292.931,68Horas acoplado h 744 5.087 189.482,14Factor de carga o utilización % 97,10 98,87 81,45Factor de operación % 100 100 84,32 Paradas automáticas no programadas 0 0 47Paradas automáticas programadas 0 0 0Paradas no programadas 0 0 25Paradas programadas 0 0 26

VANDELLÓS II

ASCÓ ENDESA G. 100%

ENDESA G. 85%, IBERDROLA G. 15%

Almaraz I Julio Acumulado Acumulado1.035,27 MW en el año a origen

Producción bruta MWh 761.909 4.207.295 222.215.822Producción neta MWh 729.819 4.054.803 213.558.588Horas acoplado h 744 4.208,5 243.489Factor de carga o utilización % 97,58 78,81 81,75Factor de operación % 100 82,73 86,12Paradas automáticas no programadas 0 3 92Paradas automáticas programadas 0 0 6Paradas no programadas 0 1 19Paradas programadas 0 0 39

Almaraz II Julio Acumulado Acumulado1.045 MW en el año a origen

Producción bruta MWh 762.427 4.963.831 218.345.250Producción neta MWh 732.786 4.781.546 210.555.312Horas acoplado h 744 4.803 234.597,5Factor de carga o utilización % 98,12 93,43 86,73Factor de operación % 100 94,42 89,76Paradas automáticas no programadas 0 1 70Paradas automáticas programadas 0 0 6Paradas no programadas 0 0 22Paradas programadas 0 0 32

ENDESA G. 36%, IBERDROLA G. 53%, UFG 11%

ENDESA G. 36%,IBERDROLA G. 53%, UFG 11%ALMARAZ

Datos revisados según la Guía UNESA para IMEX COFRENTES IBERDROLA G. 100%

CENTRALES NUCLEARESESPAÑOLAS

DATOS


- Para la Unidad I se ha considerado una potencia eléctrica bruta de 1.035,27 MWe.- Para la Unidad II se ha considerado una potencia eléctrica bruta de 1.044,45 MWe.

* Datos acumulados hasta las 00:00 h. del 6 de julio de 2013, fecha de cese definitivo de la explotación de la central, según Orden Ministerial IET/1302/2013.

Nuclear España - SNE · NUCLEAR ESPAÑA september 2013 5 INTRODUCTION N owadays, Nuclear Energy...

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