Technology Support for Long Term NP Deployment in Scope …
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Technology Support for Long Term NP Deployment in Scope of Sustainability and Climate Change Mitigation Nuclear Power Technology Development Section INPRO Dialogue Forum on the Potential of Nuclear Energy to Support the Sustainable Development Goals, Including Climate Change Mitigation IAEA Headquarters, Vienna. 6-8 June 2017
Transcript of Technology Support for Long Term NP Deployment in Scope …
Brundtland DefinitionTechnology Support for Long Term NP Deployment
in Scope of Sustainability and Climate Change Mitigation
Nuclear Power Technology Development Section
INPRO Dialogue Forum on the Potential of Nuclear Energy to Support the Sustainable Development Goals, Including Climate Change Mitigation
IAEA Headquarters, Vienna. 6-8 June 2017
Outline • NPTDS Support to
Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
• SMR • HTGR • WCRs • Non-Electric Applications
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NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
Stefano Monti – Section Head
449 in operation 11% world electricity 30% low-carbon
60 under construction (2/3 in Asia)
Energy 2016
rely on biomass 1 B people
no health care due to energy poverty
Energy Challenge
Environment Climate change
CAREM-25, HTR-PM, KLT-405, RITM-200, AHWR, NuScale,
SMART, 4S, PRISM…
ABWR, ACR 1000, AP1000, APWR, Atmea-1, CANDU 6, EPR, ESBWR, VVER 1200,
CAP1400, APR1400, HPR1000…
ADS
INNOVATIVE
SMRs
EVOLUTIONARY
NPTDS Sub-Programme Structure
Information Exchange
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations
NPTDS Support to Member States Exchange of information on all reactor technologies (LWR, HWR, FR, ADS, GCR,
SMR, Non-electric applications) TWGs Objective information to all Member States on reactor technology status and
development trends: Advanced Reactor Information System (ARIS) Reactor technology assessment and selection approaches for near-term
deployment embarking countries Technology Roadmap for SMRs and Advanced Reactor Deployments Collaborative researches (CRP, ICSP) for improving safety, reliability, analysis
methods and tools, availability and economy of advanced reactors Support to NS for development of safety standards for advanced reactors Education & Training: Workshops, Training Courses, Schools, IT tools Knowledge preservation PC-based simulators development, maintenance and distribution Toolkits for non-electrical applications and Sever Accident Management Cooperate with GIF, OECD/NEA and EC in the area of advanced reactors and
their applications
Assessment for Near Term Deployment IAEA NE-Series Document # NP-T-1.10
• Formalized process • Owner exercise • ARIS database provides technical Design
Descriptions of advanced NPPs
SMR and HTGR Technologies
Frederik Reitsma Hadid Subki
News Update on SMR Countries Recent Milestone
Argentina CAREM25 is in advanced stage of construction. Aiming for fuel loading & start-up commissioning in 2019
Canada CNSC received request to perform design reviews for several SMR designs, mostly non- water cooled, including a molten salt reactor (MSR) design
China
• HTR-PM is in advanced stage of construction. Commissioning expected in 2018. • ACP100 undertook IAEA generic reactor safety review. CNNC plans to build ACP100
in Fujian Island. • China has 3 floating SMR designs (ACP100S, ACPR50S and CAP-F)
Indonesia BATAN performing a conceptual design on experimental HTGR (10 MWth) based on the design from NUKEM-Germany and ROSATOM
Korea, Republic of SMART (100 MWe) by KAERI certified in 2012. SMART undertakes a pre-project engineering in Saudi Arabia, for near-term construction of 2 units.
Saudi Arabia • K.A.CARE performs a PPE with KAERI to prepare a construction of 2 units of SMART • An MOU between K.A.CARE and CNNC on HTGR development/deployment in KSA
Russian Federation
• Akademik Lomonosov floating NPP with 2 modules of KLT40S is in advanced stage of construction. Aiming for commissioning in 2019.
• AKME Engineering will develop a deployment plan for SVBR100, a eutectic lead bismuth cooled, fast reactor.
United Kingdom • Rolls Royce has started design activities on SMR; many organizations in the UK work on
SMR design, manufacturing and supply chain preparation • Identified potential sites for future deployment of SMR
United States of America
• NuScale (600 MWe from 12 modules) submitted for NRC design review in January 2017. Aiming for deployment in Idaho Falls.
• TVA submitted early site permit for Clinch River site, design is still open.
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SMRs Under Construction for short term deployment – the front runners …
Country Reactor Model
Commercial Start
Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2019
China HTR-PM 250 Tsinghua Univ./Harbin
2 mods, 1 turbine
Other developments of SMRs
• Canada – 4 SMR designs submitted for pre-licensing vendor design review with
the Canadian Nuclear Safety Commission (CNSC) – Aimed for deployment in remote areas – 2 x HTGRs (U-battery, UltraSafe), Terrestrial Energy integral molten
salt reactor design concept; LeadCold Reactor Inc. SEALER design concept
• United Kingdom – "ambitious" nuclear research and development program proposed – SMRs identified as a focus area to develop and to maximize the
opportunities for UK industry • Not a complete list…
– Many small startup companies developing a range of SMRs across many member states
– (about 50 SMR designs already captured in the IAEA booklet) • Many newcomer countries interested
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Development status - HTGRs
• HTR-PM construction of a commercial demonstration plant modular 2 x 250MWth; operation in 2018; dummy fuel loaded Shidao Bay, Shandong province, China
• Commercial 600MWe NPP under development feasibility review passes for 2 NPPs at Ruijin city, Jiangxi province construction expected to start in 2018 may be first approved inland NPP site
Past Experience | Current test reactors
• Wealth of past experience
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Potential to participate in the complete energy market
High temperatures (750-1000oC)
Helium coolant; Graphite moderated
Small reactor units (~100 - 650 MWth)
To be deployed as multiple modules
Low power density (typically 3-6 W/cc compared to 60-100W/cc for LWRs)
Two basic design variations – Prismatic and pebble bed design
HTGRs Characteristics
Significantly improved safety potential:
Coated particle fuel contain almost all fission products for the expected operating and postulated accident temperatures in a modular HTGR.
The failure mechanisms are decoupled and totally independent.
One coated particle failure cannot lead to the failure of a neighbouring CP, as it is only driven by the maximum fuel temperature (and a statistical process)
A failure also has no effect on the cool-ability of the fuel as a failure will not change the heat removal path.
Core design and operating parameters ensure large margins
No credible events can lead to early large release - No core melt of an all ceramic core
Decay heat removal by natural means only – can lose all the coolant and external cooling (station blackout)
Most transients are slow (develop over hours and days) and no operator actions are needed
Special attention needed to limit water ingress and to mitigate massive air ingress
Safety of HTGR technology
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and Depletion Uncertainty Analysis • Modular High Temperature Gas Cooled
Reactor Safety Design • HTGR Application for Sustainable Extraction
and Mineral Product development Processes – with NEFW-NFCM
• Example of Planned Publications • TECDOC: Improving the Understanding of
Irradiation-Creep Behaviour in Nuclear Graphite Part 1: Models and Mechanisms
• TECDOC: Graphite Oxidation in Modular HTGR
• TECDOC: Performance of German mixed Th-U and UO TRISO Fuels
Information Exchange: - TWG-GCR - Nuclear Graphite Knowledge Base - Technology Needs for Increased Operating and Accident Temperatures
Further development of HTGR training and educational simulator
specification - Training workshop - Draft specification
(unfunded)
TC support: - Indonesia experimental power reactor (BATAN and BABETEN) - KA CARE (Saudi Arabia) on HTGR Technology
Portals / DB: Support to ARIS,
HTGR knowledgebase and Nuclear Graphite
Knowledge Base
Agency support related to HTGR technology – Indonesia project
• Supported by TCAP • Indonesia did a Technical assessment including HTGRs as one of the
options studied using IAEA NE-Series Document # NP-T-1.10 • Expert missions to Indonesia
– Support Indonesia BATAN on HTGRs / the experimental power reactor
• Evaluate the Research and Development Project on HTGRs • HTR technology, fuel, safety, software • RDE concept design review
– Support Indonesia BAPETEN on HTGR licensing preparations • Modular HTGR coated particle fuel and supporting analysis for fuel performance • Modular HTGR Safety Philosophy, Safety Requirements and Evaluation • Scientific fellowships
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• Newcomer countries are expressing interest in SMRs (including that with advanced reactor technology for near term deployment)
• Main reasons (and risks) were discussed: – Better fit to their needs – Newcomers want to participate in the development of the technology – Cogeneration market – Enhanced safety characteristics – No proven track record or commercial offerings
• Division of Nuclear Power supports newcomer countries that express interest in SMRs – Use of all the mechanisms available (technical meetings, CRPs) – Member state specific needs are addressed through TC projects and
missions
Summary
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WCRs Technologies
HWRs
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations.
Information Exchange
Modelling and
Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling” in Shanghai, China
Heat Transfer, Thermal-Hydraulics and System Design for SCWRs, UK Materials and Chemistry for SCWRs
• Data Bases ARIS THERPRO
• Training Courses on: Science and Technology of SCWRs Understanding Technology and Physics of WCRs (RoK, Mexico and
Tunisia) Reactor Technology Assessment (Kenya) Use of CFD in NPP Design, SJTU, Shanghai, China
WCR Activities in 2017 • Coordinated Research Projects (CRPs) – 3 ongoing and 2 new
1. Computational Fluid Dynamics Codes for Design (2012-2018) 2. Prediction of Axial and Radial Creep in Pressure Tubes (2013-2017) 3. Thermal Hydraulics of SCWRs (2014-2018) 4. Probabilistic Safety Analysis [Benchmark] for Multi-unit, Multi-type NPP Sites (2017-2020) 5. Methodology for Developing Pipe Failure Rates for Advanced Water-cooled Reactors (2017-
2020) • International Collaborative Standard Problems (ICSPs)
1. Numerical Benchmark Database for PHWR Transients (2016-2019) • Technical Meetings on
New Concepts in Innovative Water Cooled Reactor Technology, 13 – 17 March Developing a Systematic Education and Training Approach Using Personal Computer Based
Simulators for Nuclear Power Programmes, 15 – 19 May Workshop on Advances in Understanding the Progression of Severe Accidents in BWRs, 17 –
21 July Severe Accidents Modelling and Simulations, 9 – 12 October
• Consultancy Meetings Two meetings to develop proposals for two new CRPs: Presentation Effective Utilization of THERPRO Data Base, 22 – 23 February
• Data Bases ARIS THERPRO
• Training Courses on: Understanding Physics and Technology of WCRs through Simulators: 6 new courses Reactor Technology Assessment (forthcoming Ghana) Use of CFD in NPP Design, XJTU, China
CRPs on Water Cooled Reactor Technologies
Recently Completed
SCWR Heat Transfer Behaviour and Code Testing
PHWR Radial Pressure Tube Creep Prediction Use of CFD Computer Codes for NPP Design
SCWR Thermal-Hydraulics Phenomena
METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR ADVANCED WATER- COOLED REACTORS
Fictitious PSA Model Combined (Internal Events, Internal Flooding and Fire) CDF (= 4.82E-5) Distribution by Initiator
Loss of Offsite Power 1%
Medium or Large Break LOCA 2%
Small-Break LOCA 4%
Station Blackout 5%
Loss of Support System (CCW, IA, HVAC) 1%
Loss of ESF Train 7%
Loss of DC Power 0%
Loss of Condensate, Feedwater or Condenser
Vacuum 2% Internal Flooding - Aux. Bldg. Service Water Piping System
Breach 29%
System Breach 11%
Reactor Trip ("Uncomplicated") 6%
CRP on Understanding and Prediction of Thermal- Hydraulics Phenomena Relevant to SCWRs
(2014-2018)
• Title: “Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs”, 2014-2018.
• Overall objective: – To improve the understanding of T/H phenomena and prediction accuracy of
T/H parameters related to SCWRs; and – To benchmark numerical toolsets for SCWR T/H analyses.
• 12 Participating Institutes from 10 Member States and OECD/NEA hosting the database for the CRP; and
• The 2nd RCM held at BARC, India, November 2015.
The 3rd RCM to be held in Madison, USA, June 2017.
CRP on Computational Fluid Dynamics Codes for Design (2013-2018)
• Objectives: – Assess the capabilities of CFD to address various specific design aspects through validation
benchmarks – Assess the current capabilities of advanced CFD tools to contribute to the technology advance in
NPP design – Identify and document the gaps in the technology and the state-of-the-art of CFD in respect to
being considered an essential ingredient in the design process of advanced nuclear reactors • Participants:
– 14 Institutes participating from 11 Member States • Outcomes:
– Summary Review document (document maturity of CFD in addressing design issues for NPPs) – Informal Benchmark Specifications “White Papers” – Final CRP TECDOCs (summarize benchmark results) – CFD Training Course (1st course in Shanghai, Aug 29- Sept 2 2016; 2nd in planning stage)
• Meetings: – 1st RCM July 2013, 2nd RCM February 2015, 3rd RCM October 2016 in RoKorea,
4th in VIC 2017 Oct 7-10 • Future Plans
– Document Status of CFD in NPP Design (NES) and 2 Benchmark Reports (TECDOCs) – Possibility of a Phase 2 CRP if sufficient interest in more CFD benchmarks, e.g. ABWR Lower
Plenum Temperature Distribution (discuss on Friday in LWR group)
New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor Sites
• At many nuclear sites world-wide, several NPPs, either of the same or of different types, designs, or age, are co-located on a single site.
• Regulations generally recognize the potential for multiunit accidents, PSA of NPPs have mainly focused on estimating the risk arising from damage to a single NPP.
• Safety assessments based on deterministic and probabilistic approaches in which the risk at a site with multiple reactors can be represented by summing up the risks of individual units.
• simplified approach with several limitations ignores complex interactions during a severe
event impacting a multiunit site.
Fukushima accident lesson learned: Need to improve PSA methodologies when applied to multi-unit, multi-reactor- type nuclear sites.
Several methods have are being explored around the world to extend or “translate” per-unit PSA results to multi-unit site PSA results, such as core damage and large release frequencies.
This CRP will bring together experts from LWR and PHWR MSs to benchmark their practices, compare assumptions and results and recommend improvements to the "Framework and Process for Multi-unit Site PSA" (parallel NSNI Activity).
Example – Atucha, Argentina: • 2 unique PHWRs operating • 1 SMR under construction • 1 CANDU planned • 1 PWR possible
One NPP site with five different reactor types
New CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR
ADVANCED WATER-COOLED REACTORS • Objectives:
– Increase the knowledge and understanding of the methodology in MSs on how to predict pipe failure rates for advanced WCRs that utilize the current state-of-knowledge regarding the five decades of extensive and well documented operating experience data on piping system components in operating WCRs
– Provide specific guidelines in consideration to the effect of new materials on piping reliability including the prediction of aging factor effects
– Develop common set of benchmarks
• 1st CM: – February 27 – March 2, 2017 – 4 MSs and OECD participants developed a detailed proposal for
launching the CRP in 2018
Human Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic Simulators Understanding Physics and Technology of WCRs/FRs/HTGRs
No. Year Dates Title Location Funding Organization
1 1999 November 22- 26
Workshop on Reactor Simulator Development Vienna, Austria
NPTDS
2 2000 16-27 October Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
ICTP-NPTDS
4 2002 14 - 25 October Workshop on Advanced Nuclear Power Plant Simulation
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
8 2006 3-7 July Workshop on NPP Simulators for Education Bucharest, Romania
TC Project ROM9026
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
10 2009 12 - 23 October Workshop on NPP Simulators for Education Trieste, Italy
ICTP-NPTDS
11 2011 3 - 14 October Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
NPTDS
12 2012 3-4 October Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
NPDTS
13 2013 4 - 15 November Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
14 2013 03-07 June Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
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15 2014 15-19 December Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded 24
16 2015 16-28 February Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
ICTP-NPTDS 35/ 118
17 2015 4-8 May Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded 15
18 2015 1-5 June Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded 16
20 2015 7-18 December Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded 28
21 2016 May 23- June 3 Physics and Technology of PWRs with PC-based Simulators
Daejeon, Korea
18
22 2016 11-15 July Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
14
23 2016 24-28 October Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
24 Pilot Training on WCR Technology and Severe Accidents Salt Lake City, USA Okayama University funded 13
25 IAEA/KAERI Regional Training Course on WCRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
KAERI, RoK TC and KAERI funded
26 Advanced WCRs: Physics, Technology, Passive Safety, and Basic Principle Simulators
Islamabad, Pakistan
27 IAEA/VINATOM National Training Course on PWRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
Hanoi, Viet Nam
TC and VINATOM supported
28 Technology and Physics of WCRs and SMRs with PC based Simulators KAERI for Saudi Arabia
TC and Saudi Arabia supported
29 Understanding Technology and Physics of WCRs with the Use of PC based Simulators
ICTP Italy
2016
2017
No.
Year
Dates
Title
Location
Vienna, Austria
Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Bucharest, Romania
Trieste, Italy
Trieste, Italy
3 - 14 October
Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
4 - 15 November
Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
TC Inter-regional
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded
16-28 February
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded
7-18 December
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded
Daejeon, Korea
11-15 July
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
24-28 October
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
TRAINING COURSES REACTOR TECHNOLOGY
ASSESSMENT A formal process of specifying key factors, based on country-specific protocols, assigning relative importance to each, and quantitatively evaluating each design in a consistent manner using reliable and comparable data, e.g. from ARIS and from vendors.
Recently conducted in: • Kenya (2016) • Mexico, Kazakhstan (2015) • Algeria, Bangladesh, Korea (2014) In planning: • Ghana
NPTDS Support to Member States
Non-Electric Applications
Ibrahim Khamis
Rami El-Emam
Co nt
Introduction on Nuclear Cogeneration:
Nuclear Desalination
Energy Market
Non-Electric Applications & Nuclear Cogeneration
Nuclear Cogeneration for Climate Change Mitigation (1)
Current Status:
with total net electrical capacity of 392,116 MWe
This is equivalent to annual reduction of 1 - 2 Million tonnes of CO2 emissions
Based on the type of fossil fuel would be used to cover this thermal demand
Assume: ~ 25% recovery of waste heat
Nuclear Cogeneration for Climate Change Mitigation (2)
The need of Desalination?
Desalination: need energy
– Low quality steam (MED or MSF, or RO)
– Off-peak power (elect. For RO)
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– Quality industrial water
Improves overall efficiency
Nuclear Desalination: Sustainable Development
• Over 500 reactor years of operation
• The recovery of nuclear heat from present NPP is technically feasible • The primary heat transport line can be designed with low thermal losses even for
long distances, Recent developments in piping insulation allows transfer of heat for 100 km with only ∼ 2% heat loss of the transported power
• Heat recovery enhances plant efficiency, provides a high energetic gain (+70%)
• The recovered heat is economically competitive
Environment !
Nuclear Hydrogen Production
Future nuclear reactors: High-temperature electrolysis Thermochemical cycles hybrid thermochemical cycles
Promising Technologies
Saving of resources by 30-40%
Securing energy supply by reducing dependency on foreign oil uncertainties
Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration
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DEEP can be used for performance and cost evaluation of various power and seawater desalination cogeneration configurations.
DE-TOP models the steam power cycle (Rankine cycle) of different water cooled reactors or fossil plants, and coupling with other non-electrical applications.
HEEP is to Evaluates the economics of the most promising processes for hydrogen production TOOLKITS
Ongoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)
IAEA Project on Non-Electric Applications
CRP on Assessing Technical and Economic Aspects of Nuclear Hydrogen Production for Near- Term Deployment (starts 2018)
Coordinated Research Programs CRP
Technical Meetings TM
Technical Meeting to Examine the Techno-Economics of and Opportunities for Non- Electric Applications of Small and Medium-Sized or Modular Reactors, Vienna, 29-31 May.
Technical Meeting to Examine the Role of Nuclear Hydrogen Production in the Context of the Hydrogen Economy, Vienna, 17–19 July 2017
6th TM of the Technical Working Group on Nuclear Desalination (TWG-ND), 13-15 November 2017(closed to TWG-ND members)
Technical Meeting on the Responsibilities of Users and Vendors in Nuclear Desalination Projects, VIC, 20-22 Nov
Activities on Non-Electric Applications
Summary
A great opportunity for non-electric applications using nuclear power exists in the heat and transportation market.
Nuclear Cogeneration provide many incentives for better NPP economics, environment, and electrical grids.
Thank you!
Time for questions and discussions!
Technology Support for Long Term NP Deployment in Scope of Sustainability and Climate Change Mitigation
Outline
NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
NPP in the World(as of 2 May 2017)
Slide Number 5
NPTDS Support to Member States
Evolutionary, SMR and Innovative Reactors
IAEA Technology Assessment
News Update on SMR
SMRs Under Construction for short term deployment – the front runners …
Other developments of SMRs
Agency support related to HTGR technology – Indonesia project
Summary
WCR Technology Development Team Core Business
WCR Activities in 2016
WCR Activities in 2017
CRP on Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs (2014-2018)
CRP on Computational Fluid Dynamics Codes for Design (2013-2018)
New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor Sites
New CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FORADVANCED WATER-COOLED REACTORS
Human Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic SimulatorsUnderstanding Physics and Technology of WCRs/FRs/HTGRs
TRAINING COURSESREACTOR TECHNOLOGY ASSESSMENT
NPTDS Support to Member States Non-Electric Applications
Contents
Nuclear Desalination from Waste Heat
Slide Number 45
Slide Number 47
Slide Number 48
Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration
Ongoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)
Slide Number 51
Nuclear Power Technology Development Section
INPRO Dialogue Forum on the Potential of Nuclear Energy to Support the Sustainable Development Goals, Including Climate Change Mitigation
IAEA Headquarters, Vienna. 6-8 June 2017
Outline • NPTDS Support to
Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
• SMR • HTGR • WCRs • Non-Electric Applications
2
NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
Stefano Monti – Section Head
449 in operation 11% world electricity 30% low-carbon
60 under construction (2/3 in Asia)
Energy 2016
rely on biomass 1 B people
no health care due to energy poverty
Energy Challenge
Environment Climate change
CAREM-25, HTR-PM, KLT-405, RITM-200, AHWR, NuScale,
SMART, 4S, PRISM…
ABWR, ACR 1000, AP1000, APWR, Atmea-1, CANDU 6, EPR, ESBWR, VVER 1200,
CAP1400, APR1400, HPR1000…
ADS
INNOVATIVE
SMRs
EVOLUTIONARY
NPTDS Sub-Programme Structure
Information Exchange
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations
NPTDS Support to Member States Exchange of information on all reactor technologies (LWR, HWR, FR, ADS, GCR,
SMR, Non-electric applications) TWGs Objective information to all Member States on reactor technology status and
development trends: Advanced Reactor Information System (ARIS) Reactor technology assessment and selection approaches for near-term
deployment embarking countries Technology Roadmap for SMRs and Advanced Reactor Deployments Collaborative researches (CRP, ICSP) for improving safety, reliability, analysis
methods and tools, availability and economy of advanced reactors Support to NS for development of safety standards for advanced reactors Education & Training: Workshops, Training Courses, Schools, IT tools Knowledge preservation PC-based simulators development, maintenance and distribution Toolkits for non-electrical applications and Sever Accident Management Cooperate with GIF, OECD/NEA and EC in the area of advanced reactors and
their applications
Assessment for Near Term Deployment IAEA NE-Series Document # NP-T-1.10
• Formalized process • Owner exercise • ARIS database provides technical Design
Descriptions of advanced NPPs
SMR and HTGR Technologies
Frederik Reitsma Hadid Subki
News Update on SMR Countries Recent Milestone
Argentina CAREM25 is in advanced stage of construction. Aiming for fuel loading & start-up commissioning in 2019
Canada CNSC received request to perform design reviews for several SMR designs, mostly non- water cooled, including a molten salt reactor (MSR) design
China
• HTR-PM is in advanced stage of construction. Commissioning expected in 2018. • ACP100 undertook IAEA generic reactor safety review. CNNC plans to build ACP100
in Fujian Island. • China has 3 floating SMR designs (ACP100S, ACPR50S and CAP-F)
Indonesia BATAN performing a conceptual design on experimental HTGR (10 MWth) based on the design from NUKEM-Germany and ROSATOM
Korea, Republic of SMART (100 MWe) by KAERI certified in 2012. SMART undertakes a pre-project engineering in Saudi Arabia, for near-term construction of 2 units.
Saudi Arabia • K.A.CARE performs a PPE with KAERI to prepare a construction of 2 units of SMART • An MOU between K.A.CARE and CNNC on HTGR development/deployment in KSA
Russian Federation
• Akademik Lomonosov floating NPP with 2 modules of KLT40S is in advanced stage of construction. Aiming for commissioning in 2019.
• AKME Engineering will develop a deployment plan for SVBR100, a eutectic lead bismuth cooled, fast reactor.
United Kingdom • Rolls Royce has started design activities on SMR; many organizations in the UK work on
SMR design, manufacturing and supply chain preparation • Identified potential sites for future deployment of SMR
United States of America
• NuScale (600 MWe from 12 modules) submitted for NRC design review in January 2017. Aiming for deployment in Idaho Falls.
• TVA submitted early site permit for Clinch River site, design is still open.
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SMRs Under Construction for short term deployment – the front runners …
Country Reactor Model
Commercial Start
Argentina CAREM-25 27 CNEA 1 Near the Atucha-2 site 2019
China HTR-PM 250 Tsinghua Univ./Harbin
2 mods, 1 turbine
Other developments of SMRs
• Canada – 4 SMR designs submitted for pre-licensing vendor design review with
the Canadian Nuclear Safety Commission (CNSC) – Aimed for deployment in remote areas – 2 x HTGRs (U-battery, UltraSafe), Terrestrial Energy integral molten
salt reactor design concept; LeadCold Reactor Inc. SEALER design concept
• United Kingdom – "ambitious" nuclear research and development program proposed – SMRs identified as a focus area to develop and to maximize the
opportunities for UK industry • Not a complete list…
– Many small startup companies developing a range of SMRs across many member states
– (about 50 SMR designs already captured in the IAEA booklet) • Many newcomer countries interested
18
Development status - HTGRs
• HTR-PM construction of a commercial demonstration plant modular 2 x 250MWth; operation in 2018; dummy fuel loaded Shidao Bay, Shandong province, China
• Commercial 600MWe NPP under development feasibility review passes for 2 NPPs at Ruijin city, Jiangxi province construction expected to start in 2018 may be first approved inland NPP site
Past Experience | Current test reactors
• Wealth of past experience
19
Potential to participate in the complete energy market
High temperatures (750-1000oC)
Helium coolant; Graphite moderated
Small reactor units (~100 - 650 MWth)
To be deployed as multiple modules
Low power density (typically 3-6 W/cc compared to 60-100W/cc for LWRs)
Two basic design variations – Prismatic and pebble bed design
HTGRs Characteristics
Significantly improved safety potential:
Coated particle fuel contain almost all fission products for the expected operating and postulated accident temperatures in a modular HTGR.
The failure mechanisms are decoupled and totally independent.
One coated particle failure cannot lead to the failure of a neighbouring CP, as it is only driven by the maximum fuel temperature (and a statistical process)
A failure also has no effect on the cool-ability of the fuel as a failure will not change the heat removal path.
Core design and operating parameters ensure large margins
No credible events can lead to early large release - No core melt of an all ceramic core
Decay heat removal by natural means only – can lose all the coolant and external cooling (station blackout)
Most transients are slow (develop over hours and days) and no operator actions are needed
Special attention needed to limit water ingress and to mitigate massive air ingress
Safety of HTGR technology
22
and Depletion Uncertainty Analysis • Modular High Temperature Gas Cooled
Reactor Safety Design • HTGR Application for Sustainable Extraction
and Mineral Product development Processes – with NEFW-NFCM
• Example of Planned Publications • TECDOC: Improving the Understanding of
Irradiation-Creep Behaviour in Nuclear Graphite Part 1: Models and Mechanisms
• TECDOC: Graphite Oxidation in Modular HTGR
• TECDOC: Performance of German mixed Th-U and UO TRISO Fuels
Information Exchange: - TWG-GCR - Nuclear Graphite Knowledge Base - Technology Needs for Increased Operating and Accident Temperatures
Further development of HTGR training and educational simulator
specification - Training workshop - Draft specification
(unfunded)
TC support: - Indonesia experimental power reactor (BATAN and BABETEN) - KA CARE (Saudi Arabia) on HTGR Technology
Portals / DB: Support to ARIS,
HTGR knowledgebase and Nuclear Graphite
Knowledge Base
Agency support related to HTGR technology – Indonesia project
• Supported by TCAP • Indonesia did a Technical assessment including HTGRs as one of the
options studied using IAEA NE-Series Document # NP-T-1.10 • Expert missions to Indonesia
– Support Indonesia BATAN on HTGRs / the experimental power reactor
• Evaluate the Research and Development Project on HTGRs • HTR technology, fuel, safety, software • RDE concept design review
– Support Indonesia BAPETEN on HTGR licensing preparations • Modular HTGR coated particle fuel and supporting analysis for fuel performance • Modular HTGR Safety Philosophy, Safety Requirements and Evaluation • Scientific fellowships
23
• Newcomer countries are expressing interest in SMRs (including that with advanced reactor technology for near term deployment)
• Main reasons (and risks) were discussed: – Better fit to their needs – Newcomers want to participate in the development of the technology – Cogeneration market – Enhanced safety characteristics – No proven track record or commercial offerings
• Division of Nuclear Power supports newcomer countries that express interest in SMRs – Use of all the mechanisms available (technical meetings, CRPs) – Member state specific needs are addressed through TC projects and
missions
Summary
24
WCRs Technologies
HWRs
Assist MSs with national nuclear programmes; Support innovations in nuclear power deployment; Facilitate and assist international R&D collaborations.
Information Exchange
Modelling and
Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling” in Shanghai, China
Heat Transfer, Thermal-Hydraulics and System Design for SCWRs, UK Materials and Chemistry for SCWRs
• Data Bases ARIS THERPRO
• Training Courses on: Science and Technology of SCWRs Understanding Technology and Physics of WCRs (RoK, Mexico and
Tunisia) Reactor Technology Assessment (Kenya) Use of CFD in NPP Design, SJTU, Shanghai, China
WCR Activities in 2017 • Coordinated Research Projects (CRPs) – 3 ongoing and 2 new
1. Computational Fluid Dynamics Codes for Design (2012-2018) 2. Prediction of Axial and Radial Creep in Pressure Tubes (2013-2017) 3. Thermal Hydraulics of SCWRs (2014-2018) 4. Probabilistic Safety Analysis [Benchmark] for Multi-unit, Multi-type NPP Sites (2017-2020) 5. Methodology for Developing Pipe Failure Rates for Advanced Water-cooled Reactors (2017-
2020) • International Collaborative Standard Problems (ICSPs)
1. Numerical Benchmark Database for PHWR Transients (2016-2019) • Technical Meetings on
New Concepts in Innovative Water Cooled Reactor Technology, 13 – 17 March Developing a Systematic Education and Training Approach Using Personal Computer Based
Simulators for Nuclear Power Programmes, 15 – 19 May Workshop on Advances in Understanding the Progression of Severe Accidents in BWRs, 17 –
21 July Severe Accidents Modelling and Simulations, 9 – 12 October
• Consultancy Meetings Two meetings to develop proposals for two new CRPs: Presentation Effective Utilization of THERPRO Data Base, 22 – 23 February
• Data Bases ARIS THERPRO
• Training Courses on: Understanding Physics and Technology of WCRs through Simulators: 6 new courses Reactor Technology Assessment (forthcoming Ghana) Use of CFD in NPP Design, XJTU, China
CRPs on Water Cooled Reactor Technologies
Recently Completed
SCWR Heat Transfer Behaviour and Code Testing
PHWR Radial Pressure Tube Creep Prediction Use of CFD Computer Codes for NPP Design
SCWR Thermal-Hydraulics Phenomena
METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR ADVANCED WATER- COOLED REACTORS
Fictitious PSA Model Combined (Internal Events, Internal Flooding and Fire) CDF (= 4.82E-5) Distribution by Initiator
Loss of Offsite Power 1%
Medium or Large Break LOCA 2%
Small-Break LOCA 4%
Station Blackout 5%
Loss of Support System (CCW, IA, HVAC) 1%
Loss of ESF Train 7%
Loss of DC Power 0%
Loss of Condensate, Feedwater or Condenser
Vacuum 2% Internal Flooding - Aux. Bldg. Service Water Piping System
Breach 29%
System Breach 11%
Reactor Trip ("Uncomplicated") 6%
CRP on Understanding and Prediction of Thermal- Hydraulics Phenomena Relevant to SCWRs
(2014-2018)
• Title: “Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs”, 2014-2018.
• Overall objective: – To improve the understanding of T/H phenomena and prediction accuracy of
T/H parameters related to SCWRs; and – To benchmark numerical toolsets for SCWR T/H analyses.
• 12 Participating Institutes from 10 Member States and OECD/NEA hosting the database for the CRP; and
• The 2nd RCM held at BARC, India, November 2015.
The 3rd RCM to be held in Madison, USA, June 2017.
CRP on Computational Fluid Dynamics Codes for Design (2013-2018)
• Objectives: – Assess the capabilities of CFD to address various specific design aspects through validation
benchmarks – Assess the current capabilities of advanced CFD tools to contribute to the technology advance in
NPP design – Identify and document the gaps in the technology and the state-of-the-art of CFD in respect to
being considered an essential ingredient in the design process of advanced nuclear reactors • Participants:
– 14 Institutes participating from 11 Member States • Outcomes:
– Summary Review document (document maturity of CFD in addressing design issues for NPPs) – Informal Benchmark Specifications “White Papers” – Final CRP TECDOCs (summarize benchmark results) – CFD Training Course (1st course in Shanghai, Aug 29- Sept 2 2016; 2nd in planning stage)
• Meetings: – 1st RCM July 2013, 2nd RCM February 2015, 3rd RCM October 2016 in RoKorea,
4th in VIC 2017 Oct 7-10 • Future Plans
– Document Status of CFD in NPP Design (NES) and 2 Benchmark Reports (TECDOCs) – Possibility of a Phase 2 CRP if sufficient interest in more CFD benchmarks, e.g. ABWR Lower
Plenum Temperature Distribution (discuss on Friday in LWR group)
New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor Sites
• At many nuclear sites world-wide, several NPPs, either of the same or of different types, designs, or age, are co-located on a single site.
• Regulations generally recognize the potential for multiunit accidents, PSA of NPPs have mainly focused on estimating the risk arising from damage to a single NPP.
• Safety assessments based on deterministic and probabilistic approaches in which the risk at a site with multiple reactors can be represented by summing up the risks of individual units.
• simplified approach with several limitations ignores complex interactions during a severe
event impacting a multiunit site.
Fukushima accident lesson learned: Need to improve PSA methodologies when applied to multi-unit, multi-reactor- type nuclear sites.
Several methods have are being explored around the world to extend or “translate” per-unit PSA results to multi-unit site PSA results, such as core damage and large release frequencies.
This CRP will bring together experts from LWR and PHWR MSs to benchmark their practices, compare assumptions and results and recommend improvements to the "Framework and Process for Multi-unit Site PSA" (parallel NSNI Activity).
Example – Atucha, Argentina: • 2 unique PHWRs operating • 1 SMR under construction • 1 CANDU planned • 1 PWR possible
One NPP site with five different reactor types
New CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FOR
ADVANCED WATER-COOLED REACTORS • Objectives:
– Increase the knowledge and understanding of the methodology in MSs on how to predict pipe failure rates for advanced WCRs that utilize the current state-of-knowledge regarding the five decades of extensive and well documented operating experience data on piping system components in operating WCRs
– Provide specific guidelines in consideration to the effect of new materials on piping reliability including the prediction of aging factor effects
– Develop common set of benchmarks
• 1st CM: – February 27 – March 2, 2017 – 4 MSs and OECD participants developed a detailed proposal for
launching the CRP in 2018
Human Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic Simulators Understanding Physics and Technology of WCRs/FRs/HTGRs
No. Year Dates Title Location Funding Organization
1 1999 November 22- 26
Workshop on Reactor Simulator Development Vienna, Austria
NPTDS
2 2000 16-27 October Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
ICTP-NPTDS
4 2002 14 - 25 October Workshop on Advanced Nuclear Power Plant Simulation
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
8 2006 3-7 July Workshop on NPP Simulators for Education Bucharest, Romania
TC Project ROM9026
Workshop on Nuclear Power Plant Simulators for Education
Trieste, Italy
ICTP-NPTDS
10 2009 12 - 23 October Workshop on NPP Simulators for Education Trieste, Italy
ICTP-NPTDS
11 2011 3 - 14 October Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
NPTDS
12 2012 3-4 October Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
NPDTS
13 2013 4 - 15 November Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
14 2013 03-07 June Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
27
15 2014 15-19 December Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded 24
16 2015 16-28 February Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
ICTP-NPTDS 35/ 118
17 2015 4-8 May Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded 15
18 2015 1-5 June Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded 16
20 2015 7-18 December Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded 28
21 2016 May 23- June 3 Physics and Technology of PWRs with PC-based Simulators
Daejeon, Korea
18
22 2016 11-15 July Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
14
23 2016 24-28 October Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
24 Pilot Training on WCR Technology and Severe Accidents Salt Lake City, USA Okayama University funded 13
25 IAEA/KAERI Regional Training Course on WCRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
KAERI, RoK TC and KAERI funded
26 Advanced WCRs: Physics, Technology, Passive Safety, and Basic Principle Simulators
Islamabad, Pakistan
27 IAEA/VINATOM National Training Course on PWRs Technologies and Passive Systems: Competence Based Approach with PC-Based Basic Principle Simulators
Hanoi, Viet Nam
TC and VINATOM supported
28 Technology and Physics of WCRs and SMRs with PC based Simulators KAERI for Saudi Arabia
TC and Saudi Arabia supported
29 Understanding Technology and Physics of WCRs with the Use of PC based Simulators
ICTP Italy
2016
2017
No.
Year
Dates
Title
Location
Vienna, Austria
Workshop on the Application and Development of Advanced Nuclear Reactor Simulators for Educational Purposes
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Trieste, Italy
Bucharest, Romania
Trieste, Italy
Trieste, Italy
3 - 14 October
Workshop on Enhancing Nuclear Engineering through the Use of the IAEA PC-based Nuclear Power Plant Simulators
Milano, Italy
Present paper at European Nuclear Power Plant Simulation Forum 2012
Barcelona, Spain
4 - 15 November
Course on Physics and Technology of Water Cooled Reactors through the Use of PC-Based Simulators
Madrid, Spain
In cooperation
Interregional Course on Fundamentals of Pressurized Water Reactors with PC-Based Simulators
Daejeon, Korea
TC Inter-regional
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Bangi, MALAYSIA
TC Funded
16-28 February
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
Trieste, Italy
Understanding the Physics and Technology of Advanced Passively Safe Water-Cooled Nuclear Reactors using Basic Principles Simulators
Santiago, CHILE
TC Funded
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Daejeon, Korea
Course on Fundamentals of Pressurized Water Reactors with PC-based Simulators
Amman, Jordan
TC Funded
7-18 December
Physics and Technology of Water-Cooled Reactors through the use of PC-based Simulators
TAMU, Texas
TC Funded
Daejeon, Korea
11-15 July
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Tunis, Tunisia
24-28 October
Understanding the Physics and Technology of PWRs through the use of PC-based Simulators
Ocoyoacac, Mexico
TC Funded
TRAINING COURSES REACTOR TECHNOLOGY
ASSESSMENT A formal process of specifying key factors, based on country-specific protocols, assigning relative importance to each, and quantitatively evaluating each design in a consistent manner using reliable and comparable data, e.g. from ARIS and from vendors.
Recently conducted in: • Kenya (2016) • Mexico, Kazakhstan (2015) • Algeria, Bangladesh, Korea (2014) In planning: • Ghana
NPTDS Support to Member States
Non-Electric Applications
Ibrahim Khamis
Rami El-Emam
Co nt
Introduction on Nuclear Cogeneration:
Nuclear Desalination
Energy Market
Non-Electric Applications & Nuclear Cogeneration
Nuclear Cogeneration for Climate Change Mitigation (1)
Current Status:
with total net electrical capacity of 392,116 MWe
This is equivalent to annual reduction of 1 - 2 Million tonnes of CO2 emissions
Based on the type of fossil fuel would be used to cover this thermal demand
Assume: ~ 25% recovery of waste heat
Nuclear Cogeneration for Climate Change Mitigation (2)
The need of Desalination?
Desalination: need energy
– Low quality steam (MED or MSF, or RO)
– Off-peak power (elect. For RO)
43
– Quality industrial water
Improves overall efficiency
Nuclear Desalination: Sustainable Development
• Over 500 reactor years of operation
• The recovery of nuclear heat from present NPP is technically feasible • The primary heat transport line can be designed with low thermal losses even for
long distances, Recent developments in piping insulation allows transfer of heat for 100 km with only ∼ 2% heat loss of the transported power
• Heat recovery enhances plant efficiency, provides a high energetic gain (+70%)
• The recovered heat is economically competitive
Environment !
Nuclear Hydrogen Production
Future nuclear reactors: High-temperature electrolysis Thermochemical cycles hybrid thermochemical cycles
Promising Technologies
Saving of resources by 30-40%
Securing energy supply by reducing dependency on foreign oil uncertainties
Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration
49
DEEP can be used for performance and cost evaluation of various power and seawater desalination cogeneration configurations.
DE-TOP models the steam power cycle (Rankine cycle) of different water cooled reactors or fossil plants, and coupling with other non-electrical applications.
HEEP is to Evaluates the economics of the most promising processes for hydrogen production TOOLKITS
Ongoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)
IAEA Project on Non-Electric Applications
CRP on Assessing Technical and Economic Aspects of Nuclear Hydrogen Production for Near- Term Deployment (starts 2018)
Coordinated Research Programs CRP
Technical Meetings TM
Technical Meeting to Examine the Techno-Economics of and Opportunities for Non- Electric Applications of Small and Medium-Sized or Modular Reactors, Vienna, 29-31 May.
Technical Meeting to Examine the Role of Nuclear Hydrogen Production in the Context of the Hydrogen Economy, Vienna, 17–19 July 2017
6th TM of the Technical Working Group on Nuclear Desalination (TWG-ND), 13-15 November 2017(closed to TWG-ND members)
Technical Meeting on the Responsibilities of Users and Vendors in Nuclear Desalination Projects, VIC, 20-22 Nov
Activities on Non-Electric Applications
Summary
A great opportunity for non-electric applications using nuclear power exists in the heat and transportation market.
Nuclear Cogeneration provide many incentives for better NPP economics, environment, and electrical grids.
Thank you!
Time for questions and discussions!
Technology Support for Long Term NP Deployment in Scope of Sustainability and Climate Change Mitigation
Outline
NPTDS Support to Member States in Nuclear Reactor Technology Assessment for Near Term Deployment
NPP in the World(as of 2 May 2017)
Slide Number 5
NPTDS Support to Member States
Evolutionary, SMR and Innovative Reactors
IAEA Technology Assessment
News Update on SMR
SMRs Under Construction for short term deployment – the front runners …
Other developments of SMRs
Agency support related to HTGR technology – Indonesia project
Summary
WCR Technology Development Team Core Business
WCR Activities in 2016
WCR Activities in 2017
CRP on Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWRs (2014-2018)
CRP on Computational Fluid Dynamics Codes for Design (2013-2018)
New CRP on Probabilistic Safety Analysis (PSA) for Multi-Unit, Multi-Reactor Sites
New CRP on METHODOLOGY FOR DEVELOPING PIPE FAILURE RATES FORADVANCED WATER-COOLED REACTORS
Human Capacity Building: Active Learning with Education and Training Courses Using PC Based Basic SimulatorsUnderstanding Physics and Technology of WCRs/FRs/HTGRs
TRAINING COURSESREACTOR TECHNOLOGY ASSESSMENT
NPTDS Support to Member States Non-Electric Applications
Contents
Nuclear Desalination from Waste Heat
Slide Number 45
Slide Number 47
Slide Number 48
Tools & Toolkits on Non-Electric Applications and Nuclear Cogeneration
Ongoing CRP on Application of advanced low temperature desalination systems to support NPPs and non-electric applications (2012-2017)
Slide Number 51
