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APPLYING ADVANCED SCIENCE TO A COMPLEX WORLD.

Canadian Nuclear Laboratories (formerly AECL) is a world leader in nuclear science and technology; with a proud history of innovation and a world of opportunity ahead.

Leverage our expertise and facilities to improve the competitiveness of your organization. For more information visit www.cnl.ca.

NOUS APPLIQUONS DES PRINCIPES SCIENTIFIQUES DANS UN MONDE COMPLEXE.

Les Laboratoires Nucléaires Canadiens sont un chef de file mondial en technologie et en sciences nucléaires.

Tirer parti de notre expertise et de nos installations pour accroître la compétitivité de votre organisme au moyen d’efforts novateurs en recherche et en développement. Pour obtenir de plus amples renseignements, visitez www.cnl.ca.

www.cnl.ca

Although every effort has been made to make this Pocket Program complete and accurate, there may be instances where information is

overlooked or was not ready at the time of publication. In the event that you find any errors with your name, affiliation or abstract, please send an

email with changes to [email protected]

For the most up-to-date program schedule, please go to:http://cnsconference2015.org/proceedings

or scan this code

35th Annual CNS Conference 39th CNS/CNA Student Conference

Hilton Saint John / Saint John Trade and Convention Center 1 Market Square, Saint John, New Brunswick E2L 4Z6

May 31 - June 3, 2015 147

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SPONSORS

We are pleased to acknowledge and thank the generous financial support provided by : / Nous sommes reconnaissants du généreux

appui financier de :

Host Sponsors:

Major Conference Support:

Sponsors

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We are pleased to acknowledge and thank the generous financial support provided by : / Nous sommes reconnaissants du généreux

appui financier de :

SPONSORS

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EXHIBITS / EXPOSITION

COH Inc.

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EXHIBITS / EXPOSITION

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1 Cameco Fuel Manufacturing

2 Babcock & Wilcox Canada Ltd.

3 Babcock & Wilcox Canada Ltd.

4 Nuclear Waste Management Organization

5 WorleyParsons

6 ALARA Consultants Inc.

7 Schneider Electric

8 Canadian Institute for Non-De-structive Evaluation

9 AZZ Nuclear

10 Canadian Nuclear Laboratories

11 GE-Hitachi Nuclear Energy Canada

12 EnergySolutions Canada

13 Liburdi Automation Inc.

14 Canadian Nuclear Partners

15 Laker Energy Products Ltd.

16 Kinectrics Inc.

17 Kinectrics Inc.

18 PLC Fire Safety Solutions

19 Ian Martin Limited

20 Westinghouse Electric Company

21 Canadian Nuclear Safety Com-mission

22 SNC-Lavalin Nuclear

23 Ahlberg Cameras

24 Canberra

25 AREVA NP Canada Ltd.

35 Applus RTD

36 Canadian Nuclear Revitalization Partners

37 Golder Associates

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39 Innovation Canada Alliance

40 WiN-Canada/NA-YGN

41 Alberici Constructors, Ltd./Lorneville Mechanical Con-tractors, Ltd./Sunny Corner Enterprises, Inc.

42 Tetra Tech

FOYER

26 COH Inc.

27 Olympus

28 Systemware Innovation

29 Ritepro Corporation

30 Avasarala Technologies Inc.

31 Organization of Canadian Nucle-ar Industries

32 Curtiss-Wright Scientech

33 Kanata Electronic Services Limited

34 Sylvia Fedoruk Centre for Nucle-ar Innovation

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HONORARY CHAIR’S MESSAGE

It is my great pleasure to welcome all attendees to the historic City of Saint John, New Brunswick on the Bay of Fundy for the Canadian Nuclear Society’s 35th Annual Conference.

It has been said that the Nuclear Industry is characterized by the depth of our collaboration. This is in part because we share a global reputation that demands it, but also because it is very much in our nature. We share because we

understand that we will only be better when we do. It both defines us and it makes us all stronger. This is why gathering here to exchange views, ideas and information on the application and advancement of nuclear science and technology is so very important. It helps us build on our core strengths, it helps us improve, it propels us to a better, safer future.

NB Power is committed to ensuring the reliability and diversity of our energy supply and applying innovative new ways to support emerging renewable energy sources. We believe that nuclear energy is a key to sustaining our way of life as a society while the world struggles to limit the impacts of greenhouse gases on accelerating climate change. So, every time we get together like this, there is something very much at stake – our future.

Our station, Point Lepreau Nuclear Generating Station, is not only an integral part of the local energy mix, it is also an integral part of New Brunswick’s economy. It produces enough electricity to power more than 333,000 homes per year and is a foundational piece of both our domestic energy supply and our export sales. It is a major component of the generating assets that will contribute to the provincial goal of having as much as 75 percent of the electricity used in New Brunswick coming from clean, renewable or non-emitting sources by 2020.

The more than 800 people employed at Point Lepreau provide the region with over $70 million in income and establish a solid base for the region’s nuclear research and production community. Our hope for this conference is the hospitality of our fine city and our employees will serve to inspire exchanges and insights into a shared future where energy and innovation are synonymous.

I wish you a great conference. Thank you. Merci pour votre participation.

Gaëtan Thomas, Honorary Conference Chair

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CHAIR’S MESSAGE

Welcome to AnnCon 2015 and to the wonderful City of Saint John! Your participation in this conference as a sponsor, exhibitor, speaker, session chair or attendee, is crucial to our continuing success, and the CNS is very grateful. Thank you!

My Organizing Committee has worked very hard to deliver a conference that lives up to its theme - “Nuclear Innovation Through

Collaboration”. I wish to congratulate and thank them for a job well done! We have put together plenary and technical programs that touch many focus areas that set the tone for the future of nuclear science and technology in Canada. And everywhere, we are showcasing the ever growing collaboration that exists in our industry between the facility operators, the service providers and vendors, and our educational institutions throughout Canada and abroad.

Our conference theme also drove the way the team organized the conference: finding new ways to draw interest, seeking new players to enhance the conference, and looking at new opportunities for networking. You will find collaboration everywhere: the Trade Show incorporating an OCI / NB Power Supplier Event, the joint CNA-CNS Student Poster Conference, and the joint CNA-CNS Honours & Awards, to name a few.

I cannot sign off without acknowledging two organizations that have been instrumental in making this conference a success: NB Power for acting as the official host, and NWMO for being our prime sponsor. Many thanks for your contributions!

Enjoy the conference! Take the time to network with your industry colleagues. And please, talk to the many students who will be with us. They are looking up to you as they prepare to take over.

Jacques Plourde, Chair

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ORGANIZING COMMITTEE / COMITÉ ORGANISATEUR

The CNS recognizes the considerable efforts of the Organizing Committee members named below and of their respective employers in making them available to the CNS for the planning of this conference / La SNC est reconnaissante du travail considérable accompli par les membres du comité organisateur, et remercie également leurs employeurs de leur générosité.

Honorary Chair: Gaëtan Thomas (President & CEO, NB Power)

Chair: Jacques Plourde (President, CNS) ex OPG

Conference Organizer: Ben Rouben (12 & 1 Consulting) Kathleen Duguay (New Brunswick Power)

Plenary Program Co-Chairs: Peter Ozemoyah (Tyne Engineering) Keith Scott (Worley Parsons)

Technical Program Chair: Ruxandra Dranga (CNL)

Student Conference Co-Chairs: Tracy Lapping (CNS) William Cook (UNB)

Sponsorships & Exhibits Chair: Kris Mohan (WizNucleus/ex AECL)

Treasurer: Mohinder Grover (M.S. Grover & Associates) Assisted by Ken L. Smith (UNECAN)

Communication: Jeremy Whitlock, Chair (CNL) Kathleen Duguay, NB Power Representative

Guest Seating Organizer: John Roberts (JGRchem.inc)

Conference Website: Elmir Lekovic (Webroots.ca)

Conference Secretariat: Bob O’Sullivan (CNS Office) Denise Rouben (CNS Office)

Program Booklet & Proceedings: Masih Balouch (CNL) Ben Rouben (12 & 1 Consulting) Spot Media Jason Sharpe (McMaster University) Kendall Boniface (McMaster University)

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Mr. Thomas was appointed President and CEO of New Brunswick Power Corporation in 2010.

Prior to his current position, Mr. Thomas was the Vice President of NB Power Nuclear Corporation which he held since 2005. Previous to this, Mr. Thomas held the position of Vice President, NB Power Distribution and Customer Service. Gaëtan has a proven track record of close to 30 years with operations experience in many areas of our business including Generation, Transmission, Distribution and Customer Service. Mr. Thomas holds a Bachelor of Engineering Degree (Electrical) from the University of New Brunswick and is a member of the Association of Professional Engineers and Geoscientists of New Brunswick. He is a volunteer with the Knights of Columbus and enjoys coaching sports. He and his wife, Karen, are parents of four daughters.

BIOGRAPHY / BIOGRAPHIE

GAËTAN THOMAS P.Eng. MscEE

PRESIDENT AND CEO, ÉNERGIE NB POWER

HONORARY CHAIR

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Engineering and Management Consultant focused on equipment, people and processes to achieve world-class nuclear facility performance.

40 years of experience in the nuclear industry, mainly with Ontario Power Generation / Ontario Hydro, in roles related to plant operation (training, engineering, operations, work management, project management and strategic planning), including authorization by the CNSC as a Shift Supervisor at Darlington.

Currently providing Risk Control services to the Nuclear Insurance Association of Canada, the Canadian Pool of Nuclear Insurers.

Charter member of the CNS with experience at the local Branch level and with organizing CNS events with the Nuclear Operations & Maintenance Division. President of the CNS in 2014-15.


JACQUES PLOURDE P.Eng. MscEE

PRESIDENT, CANADIAN NUCLEAR SOCIETY

CONFERENCE CHAIR

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Keith is General Manager of the Nuclear Business Unit of WorleyParsons Canada. Prior to its merger with WorleyParsons, Keith was President of Atlantic Nuclear Services Inc. He has over 40 years of experience in the nuclear industry with diverse roles ranging from specialist in Reactor Safety and Licensing, training, and operational safety to the manage-ment of nuclear projects.


DR. KEITH SCOTT WORLEYPARSONS

PLENARY CO-CHAIRS

Peter has a Master’s Degree in Chemical Engineering from the Illinois Institute of Technology, and a PhD in the same field from the University of Benin, Nigeria with emphasis on the production and the kinetics of the reactions of Petroleum Products

Peter is currently the Head of the Process Systems Division for Tyne Engineering.

Before joining Tyne Engineering, Peter had worked in other regulated (Pharmaceutical) industries.

Peter has also been a professor at several universities and colleges in North America and in Africa.

Peter has served and is currently serving as member and as chairman of several professional, non-profit, and community Boards. He served as Chairman/President of several organizations including a Rotary Club, and the Parents Support Committee of the Royal Canadian Army Cadets of Brampton, Ontario.

Peter was first elected into the CNS Council in 2013. He is currently the 2nd Vice President of the Society. He is the Chair of the Intersociety Committee and represents the CNS on the Board of Engineering Institute of Canada (EIC).


DR. PETER OZEMOYAH TYNE ENGINEERING

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Ruxandra Dranga has been working at Atomic Energy of Canada Limited, now Canadian Nuclear Laboratories, since 2009 as a Reactor Physics Analyst, performing criticality safety calculations and shielding analysis in support of various operations at Chalk River Laboratories.

She holds a B.A.Sc. from University of Toronto in Engineering Science. Ruxandra has been involved with the CNS since 2009, first as Treasurer of the CNS Chalk River Branch, followed by Education and Outreach Chair and ultimately Branch Chair. She was first elected into the CNS Council in 2012. In 2013 she became the Education and Communication Committee Chair, and in 2014 the Honours and Awards Chair. Over the years, she has been involved with the organization of a number of Conferences, Technical Meetings and CNS Courses such as the Small Reactors Technical Meeting in 2010 and 2012, the Student Conference at PBNC-2014, and the Nuclear 101 course.


RUXANDRA DRANGA

CANADIAN NUCLEAR LABORATORIES

TECHNICAL PROGRAM CHAIR

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Willy Cook is an Associate Professor in UNB’s Department of Chemical Engi-neering, joining the Faculty in August 2004 after a five-year term as the Labora-tory Manager and Research Engineer for the Chair in Nuclear Engineering. He is a professional engineer with consulting, research interests and expertise in power plant chemistry and corrosion control and teaches technical elective and graduate courses related to these topics and global energy issues. Through his research programs he has been actively involved in the International Association for the Properties of Water and Steam (IAPWS) and the Generation IV International Forum (GIF) program for evaluating materials and chemistry control regimes for the next generation of nuclear power reactors. He has recently become very active in the management, research and direction of UNB’s Centre for Nuclear Energy Research (CNER), an institute on campus that undertakes nuclear research, provides consulting to the energy industry and develops commercial products for corrosion measurement and control.


WILLY COOKUNIVERSITY OF NEW BRUNSWICK

STUDENT CONFERENCE CO-CHAIRS

Tracy joined the Computational Reactor Physics Branch at Atomic Energy of Canada Limited, now known as Canadian Nuclear Laboratories, in September 2011. As Administrative Assistant she is responsible for administrative and resource support to the branch manager and staff. Tracy has many years of business management experience and has also worked in the Municipal Government sector. She is currently the Treasurer of the CNS Chalk River Branch since July 2012. She has completed the Business Administrative course at Algonquin College and the Municipal Tax Administrative course at Seneca College. Tracy has been acting as the Program Chair since October 2013 and has been active planning a conference on Fire Safety and Emergency Preparedness for the Nuclear Industry which is slated to take place in the spring of 2016 in Toronto, ON.


TRACY LAPPING CANADIAN NUCLEAR SOCIETY

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Ben Rouben has an Honours degree in Physics and Mathematics from McGill University and a Ph. D. in theoretical nuclear physics from the Massachusetts Institute of Technology. He joined AECL in 1975, working in reactor physics. From 1993 to 2006, Ben served as Manager of the Reactor Core Physics Branch at AECL.

Ben was President of the CNS in 1997-98, and is currently its Executive Director. He was elected CNS Fellow in 1999.

Ben retired from AECL in 2007 February. He is currently a consultant, and an Adjunct Professor at McMaster University and at the University of Ontario Institute of Technology. He teaches courses on various topics in Nuclear Science and Engineering in both institutions, as well as in the M.Eng. Program offered by UNENE, the University Network of Excellence in Nuclear Engineering, where he also serves as Secretary/Treasurer.


DR. BEN ROUBENFCNS PRESIDENT, 12 & 1 CONSULTING, CNS EXECUTIVE DIRECTOR

CONFERENCE ORGANIZERS

Kathleen Duguay is the Manager of Human Performance and Nuclear Disclosure Protocol for the Point Lepreau Nuclear Generating Station (PLNGS). With more than 25 years’ experience at NB Power, she has worked in the areas of health and safety, radiation protection, public relations, radiation protection, regulatory affairs, internal and external communications, community and media relations, predominantly for the nuclear division of the corporation.


KATHLEEN DUGUAY NEW BRUNSWICK POWER

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SUNDAY MAY 31/ DIMANCHE 31 MAI

15:00 CNS Annual General Meeting (Review of CNS Year & Election of CNS Council for 2015-2016)

17:00 Conference Registration; Exhibits Open

18:00 - 20:30 Conference Opening Reception

MONDAY, JUNE 1 / LUNDI 1ER JUIN

07:00 - 07:45 Speaker’s Breakfast and Conference Continental Breakfast

08:00 Welcoming Remarks & Opening of Conference: Jacques Plourde (CNS President)

08:10 Honorary Conference Chair Address (Welcome, Overview of Plenary Program), Gaëtan Thomas (President & CEO, New Brunswick Power)

08:15 - 10:00 Plenary 1A: Nuclear Power – Utility Collaborations to Improve Lifetime Performance Chair: Gaëtan Thomas (New Brunswick Power) Strategic Importance of Collaboration and Examples, Keith Miller (NBP) Collaboration Between CNP & NBP, Pierre Tremblay (CNP) Developing Technical Exchanges with C-6 Utilities, Hong Tan (CNNO) Achieving CANDU Excellence Through Collaboration, Fred Dermarkar (CANDU Owners’ Group)

10:00-10:30 Break

CONFERENCE SUMMARY / SOMMAIRE DE LA CONFÉRENCE

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MONDAY JUNE 1 / LUNDI 1ER JUIN

10:30 - 12:00 Plenary 1B: Performance Improvement Programs: Goals and Experience Chair: Sean Granville (PLGS) Panel Discussion –Goals and Experience (CANDU Utilities): Frank Guglielmi (CNP/PL) Steve Ramjist (OPG) Paul Boucher (Bruce Power) Neil Mitchell (OPG) Hong Tan (TQNPP) Q&A

12:00 Conference Luncheon & Harold A. Smith Lecture: Guest Speaker Pierre Tremblay (Canadian Nuclear Partners)

14:00 - 17:00 Nuclear-for-Everyone Seminar (included in conference fee, but preregistration required) - Session 1A1

14:00 - 17:00 OCI-NB Power Supplier Event

14:00 - 17:00 Parallel Technical Sessions 1A1-1A4, 1B1-1B4

15:20 - 15:40 Break

17:30 -19:30 Student Poster Session & Wine-&-Cheese Reception

TUESDAY, JUNE 2 / MARDI 2 JUIN

07:00 - 07:45 Speakers’ Breakfast and Conference Continental Breakfast

08:00 - 09:40 Panel Discussion on International Developments in Used Nuclear Fuel Repository Programs (co-organized with NWMO)

08:00 - 12:00 OCI-NB Power Supplier Event

08:00 - 12:00 Parallel Technical Sessions 2A1 - 2A4, 2B1 - 2B4


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TUESDAY, JUNE 2 / MARDI 2 JUIN

09:40 - 10:00 Break

12:00 - 14:00 Conference Luncheon and CNS/CNA Honours & Awards Ceremony

14:00 - 15:30 Plenary 2A: Enterprise Risk Management Chair: Joy Shikaze (WiN) Enterprise Risk Management, Chris Eaton (Enbridge) Managing Risk for a Nuclear Generator, Christine Cosby (Bruce Power) The Importance of Leadership, Gaëtan Thomas (NBP) Technical Conscience, Paul Freeman (INPO) Risk Control and Nuclear Liability, Colleen DeMerchant (NIAC) Q&A

15:30 - 16:00 Break

16:00 - 17:30 Plenary 2B: Vendor Role in a Continuously Improving Industry Chair: Ron Oberth (OCI) Panel of Nuclear Equipment and Service Vendors along with a Utility Supply Chain Manager Shawn Sarkar (Sartrex Inc.) Keith Scott (WorleyParsons) Vince Robinson (Tyne Engineering) Brian Thorne (NB Power) Scott Malcolm (SNC-Lavalin)

18:30 Banquet Reception with Music (Saint John String Quartet)

19:30 - 22:00 Conference Banquet & Entertainment (Vinyl2Bits SHOWBAND)


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WEDNESDAY, JUNE 3 / MERCREDI 3 JUIN

07:00 - 07:45 Speakers’ Breakfast and Conference Continental Breakfast

08:00 - 09:45 Plenary 3A: Waste Management and Decommissioning Chair: David Legault (WorleyParsons) Implementing Canada’s Plan for the Long-Term Management of Used Nuclear Fuel, Derek Wilson (VP Design and Construction, NWMO) Shutdown of Pickering Station, Laurie Swami (OPG) Managing Our Nuclear Legacy Liabilities, Joan Miller (CNL) Regulatory oversight of Nuclear Waste and Commissioning, Ramzi Jammal (CNSC) International Overview on Status and Future Developments in Decommissioning of NPP, Michael Siemann (Head of Division, RPRWM, OECD Nuclear Energy Agency) Q&A

09:45 - 10:15 Break

10:15 - 12:00 Plenary 3B: Developing Technologies and Resources Chair: Robert Walker (CNL) R&D at the Universities, Basma Shalaby (UNENE) Developing Technologies and Resources, Robert Walker (CNL) Professional Development and Extension Programs, George Bereznai (UOIT) The Importance of Industrial R&D and Collaboration, Robert Whalen (SNC-Lavalin) Nuclear Innovation in Saskatchewan, Neil Alexander (Sylvia Fedoruk Canadian Centre for Nuclear Innovation, U Saskatchewan)


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WEDNESDAY, JUNE 3 / MERCREDI 3 JUIN

12:00 - 14:00 Conference Luncheon: Guest Speaker Dr. John Hilborn, AECL Retired, “70th Anniversary of ZEEP and Controlled Fission in Canada”

14:00 - 15:20 Panel Discussion on Transportation of Used Nuclear Fuel (co-organized with NWMO)

14:00 - 16:40 Parallel Technical Sessions 3A1-3A4, 3B1-3B3

15:20 - 15:40 Break

17:00 End of Conference

SEE YOU 2016 JUNE 19-22 AT: 36TH CNS ANNUAL CONFERENCE & 40TH STUDENT

CONFERENCE IN BEAUTIFUL TORONTO, ON


SUNDAY MAY 31 / DIMANCHE 31 MAISUNDAY

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SUNDAY MAY 31 / DIMANCHE 31 MAI

CNS Annual General Meeting - for CNS Members 15:00-17:00 - Montagu I & II

Conference Opening Reception 18:00-20:30 - Marco Polo and Foyer

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Breakfast for Speakers & Chairs of the Day07:00-07:45 - Montagu I & II

Conference Continental Breakfast07:00-07:45 - Marco Polo & Foyer

Welcoming Remarks & Opening of Conference08:00-08:15 - Loyalist

Chair: Jacques Plourde (CNS President 2014-15)

08:10 HONORARY CONFERENCE CHAIR ADDRESS

G. T. Thomas (President & CEO, New Brunswick Power)

Engineering and Management Consultant focused on equipment, people and processes to achieve world-class nuclear facility performance.

40 years of experience in the nuclear industry, mainly with Ontario Power Generation / Ontario Hydro, in roles related to plant operation (training, engineering, operations, work management, project management and strategic planning), including authorization by the CNSC as a Shift Supervisor at Darlington.

Currently providing Risk Control services to the Nuclear Insurance Association of Canada, the Canadian Pool of Nuclear Insurers.

Charter member of the CNS with experience at the local Branch level and with organizing CNS events with the Nuclear Operations & Maintenance Division. President of the CNS in 2014-15.


JACQUES PLOURDE P.Eng. MscEE

PRESIDENT, CANADIAN NUCLEAR SOCIETY

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Plenary IA: Nuclear Power - Utility Collaborations to Improve Lifetime Performance

08:15-10:00 - LoyalistChair: Gaëtan Thomas (New Brunswick Power)

08:15 STRATEGIC IMPORTANCE OF COLLABORATION AND EXAMPLES

Keith Miller (New Brunswick Power)

08:40 COLLABORATION BETWEEN CNP AND NBP P. Tremblay (Canadian Nuclear Partners)

09:05 DEVELOPING TECHNICAL EXCHANGES WITH C-6 UTILITIES

H. Tan (CNNO)

09:30 ACHIEVING CANDU EXCELLENCE THROUGH COLLABORATION

F. Dermarkar (CANDU Owners’ Group)

Refreshment Break10:00-10:30 - Marco Polo & Foyer

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Mr. Keith Miller was the Deputy Chief Nuclear Officer for NB Power. Keith served as Board member on the Center for Nuclear Energy Research and also at COG playing an instrumental role in the formation of the Candu6 Fleet alliance. He joined Point Lepreau in 1999 as the Production Manager leading operational improvements needed for the refurbishment decision. In 2005 Keith was appointed to a Director role focused on the strategic portfolio including the new build evaluations for the ACR-1000 & ATEMA 1, also nuclear due diligence during the aborted Hydro Quebec acquisition. He supported Point Lepreau during the extended Refurbishment and Life Extension project and return to service plant.

Prior to joining NB Power Keith worked for 28 years in the UK. At Hartlepool he was licenced for commissioning and continued for 16 years in Operation to become Production Manager at Heysham 1. In 1996 he moved into corporate to lead the fleet business improvement program for British Energy, becoming a founder member the international acquisition program in the USA with AmerGen and in Canada for Bruce Power.


KEITH MILLERNEW BRUNSWICK POWER

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Pierre retired from his role as President March 31, 2015. Pierre Tremblay was appointed to the role of President, Canadian Nuclear Partners (A subsidiary of Ontario Power Generation) in November 2013. OPG is an Ontario‐based electricity generation company whose principal business is the generation and sale of electricity in Ontario. OPG’s focus is on the efficient production and sale of electricity from its generating assets, while operating in a safe, open and environmentally responsible manner. In the Canadian Nuclear industry, Pierre Tremblay is a well‐respected and dedicated leader whose most that most recent title was President of Canadian Nuclear Partners (a subsidiary of Ontario Power Generation). Previous to that Pierre was the Deputy Chief Nuclear Officer and EVP, Canadian Nuclear Partners. A Canadian Nuclear business veteran, Pierre’s extensive career at OPG has spanned over 35 years. After earning his Bachelor of Science degree at Queen’s University, Pierre joined OPG in 1977 as a chemical engineer at the Bruce Nuclear Power Development. He has assumed multiple leadership roles, including Site Vice President for Pickering B, Director of Operations and Maintenance, and Vice President of Nuclear Training. Pierre was the CNOO responsible for overseeing all operations pertaining to Ontario Power Generation’s (OPG’s) Nuclear Fleet. Pierre also works closely with various external groups including the American Nuclear Society and the IAEA. Pierre was the Senior Vice President, Nuclear Programs and Training, where he oversaw a number of key Nuclear Support functions such as Nuclear Programs, Training, Regulatory Programs, and Nuclear Security. He also acted as the primary interface between OPG and external agencies, such as the World Association of Nuclear Operators (WANO), and the Candu Owner’s Group (COG). Pierre is the former chair of the Education and Training division of the American Nuclear Society. Pierre received his MBa from University of Toronto, now the Rotman Business School in 1984. In June, 2011, Pierre was appointed to the Durham College Board of Governors. Pierre will be the incoming Chair, appointed for the 2015-2016 Academic year. In June 2013 Pierre was inducted as a fellow to the Canadian Academy of Engineering.In January 2013, Pierre was appointed to the UOIT Board of Governors.


PIERRE F. TREMBLAY

PRESIDENT, CANADIAN NUCLEAR PARTNERS

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Mr. Hong Tan is Assistant General Manager of Nuclear Power Operations Management Co. Ltd. (CNNO).

Working Experience:

1986~1998: Worked in Maintenance Department of Qinshan Nuclear Power Stations as an I&C engineer.

1998~2000: Commissioning of Chashima Nuclear Power Plant in Pakistan as an I&C engineer.

2000~2004: Worked in Maintenance Department of Third Qinshan Nuclear Power Co., Ltd. as an I&C Section Chief.

2004~2007: Worked in Maintenance Department of Third Qinshan Nuclear Power Co. Ltd. as Deputy Maintenance Manager.

2007~2009: Worked in Maintenance Department of Third Qinshan Nuclear Power Co. Ltd. as Maintenance Manager.

2009~2014: Assistant General Manager of Third Qinshan Nuclear Power Co., Ltd.

2014~present: Plant Manager, TQNPP/ General Manager Assistant of Nuclear Power Operations Management Co. Ltd. (CNNO).

Education:

1982~1986: Studied in major of Computer Application at Zhejiang University, Hangzhou, China.


HONG TAN

CNNO

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Fred Dermarkar graduated from the University of Toronto with a degree in Mechanical Engineering. He has worked in the Canadian nuclear industry since 1981, and has held a variety of senior management positions in Nuclear Engineering, including responsibility for Design Engineering, System Engineering, Component Engineering, Chemistry, Nuclear Safety Analysis and Probabilistic Risk Assessment. He retired from OPG as the Vice President of Engineering Strategy, where he played a leadership role in Canada’s response to the accident at Fukushima. He has been the president and CEO of the Candu Owners Group since February 2014.


FRED DERMARKAR

CANDU OWNERS’ GROUP

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Plenary 1B: Performance Improvement Programs: Goals and Experience - Panel Discussion

10:30-12:00 - LoyalistChair: Sean Granville (New Brunswick Power)

PANEL MEMBERS Frank Guglielmi, (PLGS)

Steve Ramjist, (OPG) Paul Boucher, (BP) Neil Mitchell, (OPG) Hong Tan, (TQNPP)

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Sean was appointed the Site Vice President and Chief Nuclear Officer at NB Power’s Point Lepreau Generating Station, February 2013. Sean is accountable for the oversight and management of Point Lepreau Generating Station’s strategic direction to achieve safe, predictable and productive nuclear performance.

Sean’s leadership and management experience is broad. During his 30 year career at Ontario Power Generation he held a wide range of executive positions and has acquired expertise in many areas including commissioning, shift, operations and maintenance, organizational effectiveness and nuclear programs.

As a professional engineer, Sean’s extensive background has included positions as Deputy Vice President, Director Operations and Maintenance and Director Nuclear Programs. He has extensive industry experience including a secondment to WANO and has served as an industry advisor for a peer review.

Sean is a member of the Board of Directors for the Canadian Nuclear Association and CANDU Owners Group.

Sean and his wife Karen are avid kayakers and skiers and are currently enjoying the east coast lifestyle in their home near Lepreau.


SEAN GRANVILLE

NEW BRUNSWICK POWER

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Since November 2013- Station Director at Point Lepreau Generating Station located near Saint

John, New Brunswick.- Point Lepreau is a 705 MWe CANDU PHWR which has undergone a

large scale refurbishment that started March 2008 and returned to commercial operation in November 2012.

From July 2010 to November 2013- Director of Operations and Maintenance at Darlington Refurbishment

responsible for preparing the shutdown, lay-up and return to service programs for all 4 units to support plant refurbishment.

- Darlington NGS is a 4 unit CANDU PHWR located east of Toronto, Ontario which is preparing to start large scale refurbishment of all 4 units starting in October 2016.

From January 2009 to June 2010- Director of Operations and Maintenance at Darlington Nuclear

Generating Station.

From February 2007 to December 2008- Liaison Engineer seconded to WANO Atlanta Center.- Qualified as Organizational Effectiveness Team Leader and Operations

Evaluator, assisting in Peer Reviews and Support Missions in numerous plants across North America.

From March 2004 to February 2007- Operations Manager at Pickering – A Nuclear Generating Station.- Pickering A is a 2 unit 540 MWe station east of Toronto, Ontario which

had restarted in November 2003 after a 5 year layup and extensive restart project.

Prior to March 2004- Various Positions at Darlington NGS including Assistant Operations

Manager and Licensed Shift Manager.


FRANK GUGLIELMI

STATION DIRECTOR, PONT LEPREAU GS

39


Stephen Ramjist is currently the Vice-President, Fleet Operations & Maintenance at Ontario Power Generation’s (OPG) Corporate Nuclear Headquarters. In this role, he has accountability for the implementation and effectiveness of programs in the areas of Operations, Maintenance, Work Management, Radiation Protection and Performance Improvement at OPG’s two nuclear sites. He also has primary responsibility for Nuclear Fleet Improvement initiatives to achieve Business Plan results.

In his 31 year career with Ontario Hydro / Ontario Power Generation, Mr. Ramjist has held senior leadership positions in Operations, Maintenance and Work Management at Pickering, Darlington and the corporate office. He was previously licensed as a Shift Manager at Pickering A and was most recently the Director – Operations & Maintenance at Darlington Nuclear when the station achieved a second consecutive industry excellence rating. In developing a broad industry perspective, Mr. Ramjist completed a 14 month secondment to the World Association of Nuclear Operators in Atlanta as an Organizational Effectiveness Team Leader performing peer reviews at nuclear stations. He started his career in Engineering, specializing in Instrumentation and Control. He holds Bachelor of Applied Science in Engineering Science and Master of Applied Science in Mechanical Engineering degrees from the University of Toronto.


STEPHEN VIDHU RAMJIST P.Eng.

ONTARIO POWER GENERATION

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Mr. Paul Boucher is the Senior Vice President of the Bruce A Generating Station at Bruce Power. Bruce Power operates the world’s largest operating nuclear generating facility and is the source of roughly 25 per cent of Ontario’s electricity. The company’s site in Tiverton, Ontario, Canada is home to eight CANDU reactors. Paul has been working on the Bruce Power site for over 25 years where early in his career he held roles within Engineering and Outage Planning. In 2005, Mr. Boucher received his License as a Shift Manager at the four unit, Bruce B Generating Station. He advanced within the company moving into the Operations Manager position, followed by Plant Manager and Site Vice President. Paul assumed the Bruce A Vice President role after commercial declaration of Unit 1 and 2 following the Restart Project.

Mr. Boucher holds a Bachelor of Engineering degree from The University of Ottawa, Ontario, Canada. Paul has three children and a very understanding wife.


PAUL BOUCHERBRUCE POWER

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Education- BASC Mechanical Engineering, University of Toronto 1981- MEng, Mechanical Engineering, University of Toronto 1988

Professional- Registered Professional Engineer

Career Path- Summer Student Work: Ontario Hydro Mechanical Research (1978 – 1981)- Junior Engineer in Training: Ontario Hydro Nuclear Generation / Technical & Training Services (1981 – 1983)- Assistant Technical Supervisor: Ontario Hydro Technical & Training Services (1983 – 1988)- Technical Supervisor: Pickering Nuclear (1988 – 1998)- Program Manager, EQ Program (1998 – 1998)- Design Engineering Manager, Pickering A (2001 – 2004)- Senior Manager, Plant Design Engineering: Pickering A (2004 – 2005)- Director, Restart Engineering, Pickering A (2005 – 2006)- Senior Manager, Plant Design Engineering, Pickering B (2006 – 2007)- Senior Manager, Plant Design Engineering, Darlington (2007 – 2009)- Senior Manager, Darlington EQ Project (2009 – 2010)- Vice President, Refurbishment Engineering (2010 – Present)

Major Projects Completed‐ Darlington Environmental Qualification Project (2009 – 2010)‐ Design Engineering for Pickering A Return to Service (2001 – 2005)


NEIL MITCHELL P.Eng


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Mr. Hong Tan is Assistant General Manager of Nuclear Power Operations Management Co. Ltd. (CNNO).

Working Experience:

1986~1998: Worked in Maintenance Department of Qinshan Nuclear Power Stations as an I&C engineer.

1998~2000: Commissioning of Chashima Nuclear Power Plant in Pakistan as an I&C engineer.

2000~2004: Worked in Maintenance Department of Third Qinshan Nuclear Power Co., Ltd. as an I&C Section Chief.

2004~2007: Worked in Maintenance Department of Third Qinshan Nuclear Power Co. Ltd. as Deputy Maintenance Manager.

2007~2009: Worked in Maintenance Department of Third Qinshan Nuclear Power Co. Ltd. as Maintenance Manager.

2009~2014: Assistant General Manager of Third Qinshan Nuclear Power Co., Ltd.

2014~present: Plant Manager, TQNPP/ General Manager Assistant of Nuclear Power Operations Management Co. Ltd. (CNNO).

Education:

1982~1986: Studied in major of Computer Application at Zhejiang University, Hangzhou, China.


HONG TAN

TQNPP

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Conference Luncheon and Harold A. Smith Lecture12:00-14:00 - Marco Polo

13:00 HAROLD A. SMITH LECTURE P. Tremblay (Canadian Nuclear Partners)

Pierre retired from his role as President March 31, 2015. Pierre Tremblay was appointed to the role of President, Canadian Nuclear Partners (A subsidiary of Ontario Power Generation) in November 2013. OPG is an Ontario‐based electricity generation company whose principal business is the generation and sale of electricity in Ontario. OPG’s focus is on the efficient production and sale of electricity from its generating assets, while operating in a safe, open and environmentally responsible manner. In the Canadian Nuclear industry, Pierre Tremblay is a well‐respected and dedicated leader whose most that most recent title was President of Canadian Nuclear Partners (a subsidiary of Ontario Power Generation). Previous to that Pierre was the Deputy Chief Nuclear Officer and EVP, Canadian Nuclear Partners. A Canadian Nuclear business veteran, Pierre’s extensive career at OPG has spanned over 35 years. After earning his Bachelor of Science degree at Queen’s University, Pierre joined OPG in 1977 as a chemical engineer at the Bruce Nuclear Power Development. He has assumed multiple leadership roles, including Site Vice President for Pickering B, Director of Operations and Maintenance, and Vice President of Nuclear Training. Pierre was the CNOO responsible for overseeing all operations pertaining to Ontario Power Generation’s (OPG’s) Nuclear Fleet. Pierre also works closely with various external groups including the American Nuclear Society and the IAEA. Pierre was the Senior Vice President, Nuclear Programs and Training, where he oversaw a number of key Nuclear Support functions such as Nuclear Programs, Training, Regulatory Programs, and Nuclear Security. He also acted as the primary interface between OPG and external agencies, such as the World Association of Nuclear Operators (WANO), and the Candu Owner’s Group (COG). Pierre is the former chair of the Education and Training division of the American Nuclear Society. Pierre received his MBa from University of Toronto, now the Rotman Business School in 1984. In June, 2011, Pierre was appointed to the Durham College Board of Governors. Pierre will be the incoming Chair, appointed for the 2015‐2016 Academic year. In June 2013 Pierre was inducted as a fellow to the Canadian Academy of Engineering.In January 2013, Pierre was appointed to the UOIT Board of Governors.


PIERRE F. TREMBLAY

PRESIDENT, CANADIAN NUCLEAR PARTNERS

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1A1 - Nuclear-for-Everyone Seminar14:00-17:00 - Loyalist

Presenter: Jeremy Whitlock, CNL

This three-hour seminar, distilled from the CNS’ popular “Nuclear 101” course, is designed for people new to the nuclear industry, or anyone seeking information to help themselves or others better un-derstand this amazing technology and its achievements. It provides an overview of energy production fundamentals, how reactors work, history of the industry in Canada, key facts worth relating to others, and information about radiation and its effects.

The course is free for conference attendees or their guests, but pre-registration is required.

1A2 - Refurbishment and Life Extension (I)14:00-15:20 - Montagu I

Co-Chairs: Dave Essensa (NB Power); David LeFrançois (GE Hitachi Nuclear Energy Canada)

14:00 - 14:20 ADVANCED SCALE CONDITIONING AGENT AND CONSOLIDATED DEPOSIT EXTRACTION PLANNING, APPLICATION EXPERIENCE, AND RESULTS AT COMANCHE PEAK UNIT 2

M. Forney, D. Ramaley (Westinghouse Electric Company), W. Bryant (Luminant Energy)

14:20 - 14:40 RTD-INCOTEST FOR EVALUATION OF CORROSION UNDER INSULATION.

J. Witts (Applus-RTD Canada)

14:40 - 15:00 SOFTWARE-BASED ANNUNCIATOR REPLACEMENT: A TALE OF TWO PROJECTS

G. Simmons (Westinghouse Electric Company)

15:00 - 15:20 THE GENERATION OF CALANDRIA TUBE (CT) INNER DIAMETER PROFILES FROM FUEL CHANNEL (FC) INSPECTION DATA

P. J. Sedran (AMEC NSS), B. Rankin (NB Power), C. Lemire (Hydro-Québec)

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Session: 1A2 - Refurbishment and Life Extension (I)Paper Abstracts / Sommaires

14:00 - 14:20 - Montagu I

ADVANCED SCALE CONDITIONING AGENT AND CONSOLIDATED DEPOSIT EXTRACTION PLANNING, APPLICATION EXPERIENCE, AND RESULTS AT COMANCHE PEAK UNIT 2

M. Forney, D. Ramaley (Westinghouse Electric Company), W. Bryant (Luminant Energy)

Advance Scale Conditioning Agent (ASCA) technology has been applied more than forty times worldwide since its inception in 2000. This technology has continually grown in popularity since its development due to the combination of several process benefits and minimal outage impacts.

Comanche Peak Unit 2 applied a Top of Tubesheet (TTS) ASCA in 2014 for partial dissolution and softening of consolidated TTS collars. In addition to the ASCA application, a Consolidated Deposit Extraction (CODE) step was applied to the TTS. CODE is a chemical treatment technology that effectively targets and dissolves “binding species” such as those containing aluminum and silicon from steam generator deposits. Since magnetite dissolution technologies are not wholly effective in removing consolidated TTS “collars,” CODE technology was developed to address this need in the industry.

This paper will discuss both the Westinghouse and utility perspective on TTS ASCA/CODE application planning, site execution, and process results.

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14:20 - 14:40 - Montagu I

RTD-INCOTEST FOR EVALUATION OF CORROSION UNDER INSULATION.

J. Witts (Applus-RTD)

RTD-Incotest or insulated component testing, a method of pulsed eddy current, is designed and developed by Applus-RTD for the detection and sizing of corrosion under insulation. RTD-Incotest measures average wall loss over an area beneath the probe. This is accomplished by measuring the decay curve of the eddy current and then utilizes a software algorithm to determine percent wall loss. If there is a verification point this can also give average remaining wall thickness. The benefits for the nuclear industry are: 1) no need to remove insulation. Only requires one verification point. 2) reduces potential exposurs/ maintains ALARA 3) Quick and accurate screening method. For exposed piping there is no need for contact with the piping. So it can be applied for high temperature or for increasing standoff to reduce exposure.

14:40 - 15:00 - Montagu I

SOFTWARE-BASED ANNUNCIATOR REPLACEMENT: A TALE OF TWO PROJECTS

G. Simmons (Westinghouse Electric Company)

Annunciator upgrade projects are often included as parts of operating plant life extension projects as the systems are old and replacement parts are difficult to source. This paper contains case studies of the software-based annunciator replacement projects at the Westinghouse SNUPPS training simulator in Pennsylvania and the Axpo Beznau nuclear power plant in Switzerland. Software-based annunciator systems can offer a number of feature enhancements including improved readability and operator awareness, easy configuration, alarm suppression features, and alarm management at operator workstations. This paper provides an overview of each project and discusses advantages, challenges, and lessons learned from both annunciator replacement projects.

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15:00 - 15:20 - Montagu I

THE GENERATION OF CALANDRIA TUBE (CT) INNER DIAMETER PROFILES FROM FUEL CHANNEL (FC) INSPECTION DATA

P. J. Sedran (AMEC NSS), B. Rankin (NB Power), C. Lemire (Hydro-Québec)

Studies of CT deformation at spacer locations, key to the development of FC deformation modelling, have been limited by the availability of gauging measurements from removed CTs. In [1], it was proposed that CT dimensional profiles could be generated using FC inspection data. Since then, the concept was investigated further by assessing: (1) the normalisation of gap measurements to the diameter of the spacer coil, (2) the validity of gap measurements from inspections of Point Lepreau and Gentilly-2, and the CT dimensional profiles generated from the inspection data. It was concluded, from the work presented in this paper, that the CT-PT gap data and the CT dimensional profiles generated using the data from the two subject inspections are reasonable.

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1A3 -Thermalhydraulics14:00-15:20 - Montagu II

Co-Chairs: Laurence Leung (CNL); Andrew Morreale (CNL)

14:00 - 14:20 INVESTIGATION OF AIR-WATER FLOW IN A HORIZONTAL PIPE WITH 90 DEGREE BENDS USING WIRE MESH SENSORS

R. C. Bowden, S. K. Yang (CNL)

14:20 - 14:40 PREDICTION OF GAS VOLUME FRACTION IN FULLY-DEVELOPED GAS-LIQUID FLOW IN A VERTICAL PIPE

A. S. M. A. Islam, N. A. Adoo, D. J. Bergstrom (University of Saskatchewan), D. F. Wang (CNL)

14:40 - 15:00 NEW CONTACT BOILING EXPERIMENTS TO EVALUATE CALANDRIA TUBE STRAIN ACCEPTANCE CRITERIA

M. El-Hawary, J. Szymanski, A. Tanase, A. Delja, A. Oussoren (CNSC), P. Neal (CNL)

15:00 - 15:20 A CLIFF EDGE EVALUATION FOR CANDU-6 BEYOND DESIGN BASIS ACCIDENTS

S. M. Kim, D. W. Kho, S.D. Yi (Nuclear Energy Services & Solutions), S. H. Kang (Nuclear Engineering Service & Solution), S. R. Kim (Nuclear Engineering Service & Solution)

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Session: 1A3 -ThermalhydraulicsPaper Abstracts / Sommaires

14:00 - 14:20 - Montagu II

INVESTIGATION OF AIR-WATER FLOW IN A HORIZONTAL PIPE WITH 90 DEGREE BENDS USING WIRE MESH SENSORS

R. C. Bowden, S. K. Yang (CNL)

Wire mesh sensors were used to investigate the void fraction distribution along a 9 meter long, 50.8 mm diameter, horizontal test section that contained two 90 degree bends. Deionised water and compressed air were used as the working fluids, with the bubbly flow regime achieved at a superficial liquid velocity of 3.5 m/s and superficial gas velocities that varied between 0.1 and 1.2 m/s. The effects of superficial gas velocity and axial location on the void fraction distribution were investigated. Bubble and slug flow patterns were identified using a probability density function analysis based on a Gaussian mixture model.

14:20 - 14:40 - Montagu II

PREDICTION OF GAS VOLUME FRACTION IN FULLY-DEVELOPED GAS-LIQUID FLOW IN A VERTICAL PIPE

A. S. M. A. Islam, N. A. Adoo, D. J. Bergstrom (University of Saskatchewan), D. F. Wang (CNL)

An Eulerian-Eulerian two-fluid model has been implemented for the prediction of the gas volume fraction profile in turbulent upward gas-liquid flow in a vertical pipe. The two-fluid transport equations are discretized using the finite volume method and a low Reynolds number k-ε turbulence model is used to predict the turbulence field for the liquid phase. The contribution to the effective turbulence by the gas phase is modeled by a bubble induced turbulent viscosity. For the fully-developed flow being considered, the gas volume fraction profile is calculated using the radial momentum balance for the bubble phase. The model potentially includes the effect of bubble size on the interphase forces and turbulence model. The results obtained are in good agreement with experimental data from the literature. The one-dimensional formulation being developed allows for the efficient assessment and further development of both turbulence and two-fluid models for multiphase flow applications in the nuclear industry.

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14:40 - 15:00 - Montagu II

NEW CONTACT BOILING EXPERIMENTS TO EVALUATECALANDRIA TUBE STRAIN ACCEPTANCE CRITERIA

M. El-Hawary, J. Szymanski, A. Tanase, A. Delja, A. Oussoren (CNSC), P. Neal (CNL)

The Canadian Nuclear Safety Commission (CNSC) has contracted the Canadian Nuclear Laboratories (CNL) to conduct additional Contact Boiling (CB) experiments with the main objective of evaluating the acceptance criterion of CalandriaTube (CT) strain limit of 2%, proposed by the industry for fuel channel integrity assessments. The test conditions are selected using analytical tools and guidance from existing CANDU Owners Group (COG) test results, so as to lead to CT strain close to this value. The experiments will also be used to evaluate the CT quench temperature correlation proposed. This paper presents conditions selected for the first three experiments, their most important results and their preliminary analysis, with a focus on the test which produced CT strain in excess of 2%.

15:00 - 15:20 - Montagu II

A CLIFF EDGE EVALUATION FOR CANDU-6 BEYOND DESIGN BASIS ACCIDENTS

S. M. Kim, D. W. Kho, S. C. You, S. Y. Choi (KHNP), S. H. Kang (Nuclear Engineering Service & Solution), S. R. Kim (Nuclear Engineering Service & Solution)

The condition of nuclear power plant in the event of station black out (SBO) accompanying large-scale natural disaster exceeding design basis accident (DBA) was evaluated. Additional scenarios were added to the evaluation to review capability of the plant to endure different conditions with different actions. The analysis resulted that the key action required from the operator was to ensure the opening of main steam safety valves (MSSVs) in the secondary side and of motor-operated valves for high pressure injection of Emergency Core Cooling System (HPECCS) to mitigate accidents or extend the cliff edge.

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1A4 - Nuclear Materials14:00-15:20 - Montagu III

Co-Chairs: William Cook (University of New Brunswick); John Roberts (JGRchem.inc)

14:00 - 14:20 MITIGATION OF END FLUX PEAKING IN CANDU FUEL BUNDLES USING NEUTRON ABSORBERS

D. Pierce, P. K. Chan (Royal Military College of Canada), W. Shen (CNSC)

14:20 - 14:40 EXPERIMENTAL AND THERMODYNAMIC ASSESSMENT OF BERYLLIUM-REPLACEMENT MATERIALS FOR CANDU® BRAZED JOINTS

K. N. Potter, G. A. Ferrier (Royal Military College of Canada), F. C. Dimayuga (CNL), E. C. Corcoran (Royal Military College of Canada)

14:40 - 15:00 A NEW NUCLEAR MATERIALS LABORATORY AT QUEEN’S UNIVERSITY

R. A. Holt, M. R. Daymond (Queen’s University)

15:00 - 15:20 A RE-EXAMINATION OF THERMODYNAMIC MODELLING OF U-RU BINARY PHASE DIAGRAM

L. C. Wang, M. H. Kaye (UOIT)


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Session: 1A4 - Nuclear MaterialsPaper Abstracts / Sommaires

14:00 - 14:20 - Montagu III

MITIGATION OF END FLUX PEAKING IN CANDU FUEL BUNDLES USING NEUTRON ABSORBERS

D. Pierce, P. K. Chan (Royal Military College of Canada), W. Shen (CNSC)

End flux peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles. These peaks lead to an increase in fission rate and therefore greater heat generation. It is known that addition of neutron absorbers into fuel bundles can help mitigate EFP, yet implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. Monte Carlo N-Particle code (MCNP) 6.1 was used to simulate the addition of a small amount of neutron absorbers strategically within the fuel pellets. This paper will present some preliminary results collected thus far.

14:20 - 14:40 - Montagu III

EXPERIMENTAL AND THERMODYNAMIC ASSESSMENT OF BERYLLIUM-REPLACEMENT MATERIALS FOR CANDU® BRAZED JOINTS

K. N. Potter, G. A. Ferrier (Royal Military College of Canada), F. C. Dimayuga (CNL), E. C. Corcoran (Royal Military College of Canada)

Currently, appendages are joined to CANDU® fuel elements via a brazing process, with beryllium as the filler material. A potential reduction in the occupational limit on airborne beryllium particulates has motivated research into alternative brazing materials. To this end, the Canadian nuclear industry has funded an initiative to identify and evaluate the suitability of several candidate brazing materials. This work describes contributions toward the assessment of alternative brazing materials from the Royal Military College of Canada (RMCC). An impact testing method was developed to evaluate the mechanical strength of candidate braze joints. Thermodynamic modelling was performed to predict the aqueous behaviour of each candidate material in CANDU coolant conditions characteristic of reactor shutdown, and corrosion experiments are underway to support modelling predictions. The results of these activities will assist in selecting a suitable replacement material for beryllium.

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14:40 - 15:00 - Montagu III

A NEW NUCLEAR MATERIALS LABORATORY AT QUEEN’S UNIVERSITY

R. A. Holt, M. R. Daymond (Queen’s University)

The Reactor Materials Testing Laboratory (RMTL) at Queen’s University and the results of commissioning tests are described. RMTL uses energetic protons (up to 8MeV) to simulate fast neutron damage in materials for reactor components. The laboratory is also capable of He implantation (up to 12 MeV) to simulate the effects of transmutation He in reactor components. The $17.5M laboratory comprises a new building, a 4MV tandem accelerator, two electron microscopes, mechanical testing and specimen preparation equipment, and a radiation detection laboratory. RMTL focusses on studying dynamic effects of irradiation (irradiation creep, irradiation growth, irradiation induced swelling, fatigue under irradiation) in-situ.

15:00 - 15:20 - Montagu III

A RE-EXAMINATION OF THERMODYNAMIC MODELLING OF U-RU BINARY PHASE DIAGRAM

L. C. Wang, M. H. Kaye (UOIT)

Ruthenium (Ru) is one of the more abundant fission products (FPs) both in fast breeder reactors and thermal reactors. Post irradiation examinations (PIE) show that both “the white metallic phase” (Mo-Tc-Ru-Rh-Pd) and “the other metallic phase” (U(Pd-Rh-Ru)3) are present in spent nuclear fuels. Todescribe this quaternary system, binary subsystems of uranium (U) with Pd, Rh, and Ru are necessary. Presently, only the U-Ru system has been thermodynamically described but with some problems. As part of research on U-Ru-Rh-Pd quaternary system, an improved consistent thermodynamic model describing the U-Ru binary phase diagram has been obtained.

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1B2 - WMD - Radiation Monitoring 15:40-17:00 - Montagu I

Co-Chairs: Mike Garamszeghy (NWMO); Peter Ottensmeyer (University of Toronto)

15:40 - 16:00 AN INTRODUCTION AND OVERVIEW OF DRAFT CSA STANDARD N288.7 GROUNDWATER PROTECTION AT CLASS I NUCLEAR FACILITIES AND URANIUM MINES AND MILLS

J. DeWilde (Golder Associates Ltd), M. Klukas, M. Audet

16:00 - 16:20 RADIOLOGICAL SITE ASSESSMENT AT SUN ROSE CLAIM UTILIZING SCANPLOT TECHNOLOGY

H. Downey (Amec Foster Wheeler)

16:20 - 16:40 SCANPLOTSM AT WHITESHELL LABORATORIES FOR SORTING OF EXPERIMENTAL CESIUM POND SOIL


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Session: 1B2 - WMD - Radiation Monitoring Paper Abstracts / Sommaires

15:40 - 16:00 - Montagu I

AN INTRODUCTION AND OVERVIEW OF DRAFT CSA STANDARD N288.7 GROUNDWATER PROTECTION AT CLASS I NUCLEAR FACILITIES AND URANIUM MINES AND MILLS

J. DeWilde (Golder Associates Ltd), M. Klukas, M. Audet

The DRAFT CSA Standard N288.7 entitled Groundwater Protection at Class I Nuclear Facilities and Uranium Mines and Mills is currently under development and is anticipated to publish in June of 2015. This draft standard identifies a process for the protection and monitoring of groundwater at nuclear facilities but may also be used at any facility (i.e. nuclear facilities that are not Class I or non-nuclear facilities). The paper discusses the background to the draft standard, the formalized methodology described in the draft standard and provides some input on implementation. The paper is intended for people that have responsibilities related to groundwater protection at facilities that may need to comply with the draft standard or any site/facility that has some form of groundwater monitoring program.

16:00 - 16:20 - Montagu I

RADIOLOGICAL SITE ASSESSMENT AT SUN ROSE CLAIM UTILIZING SCANPLOTSM TECHNOLOGY


ScanPlotSM gamma spectroscopy land survey system was utilized for the overland survey of uranium at the Sun Rose Claim in the Northwest Territories. The Sun Rose Claim is a former uranium exploration and previous investigations had identified uranium ore and waste rock. ScanPlotSM radiological scan surveys were performed utilizing a backpack system. ScanPlotSM platform utilized spectroscopy grade sodium iodide detectors configured for optimal spatial coverage and radiation detection. Survey locations were recorded using an on-board global positioning system (GPS). The radiological spectral data from the radiation detectors is automatically logged and linked with the GPS coordinates to an on-board computer to create isocontour figures using a color scale to represent radioactivity levels. The advantage of utilizing ScanPlotSM system for this assessment is that the nature and extent of uranium is provided without collecting and analyzing a large number of samples.

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16:20 - 16:40 - Montagu I

SCANSORTSM AT WHITESHELL LABORATORIES FOR SORTING OF EXPERIMENTAL CESIUM POND SOIL


The ScanSortSM soil sorting system is a unique and efficient radiological instrument used for measuring and sorting bulk soils and volumetric materials. The system performs automatic radioassay and segregation of preconditioned material using a gamma spectroscopy system mounted above a conveyor belt. It was deployed to the Whiteshell Laboratories site to process the excavated soils generated during the decommissioning of the former Experimental Cesium Pond. The ScanSortSM system was utilized to segregate material with Cs-137 concentrations above the established site unrestricted release and restricted site reuse levels as well as demonstrated the ability to accurately determine the radioactivity concentrations of the radiologically-impacted material and to confidently segregate volumes of that material for appropriate final disposition.

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1B3 - Safety and Licensing (I) 15:40-17:00 - Montagu II

Co-Chairs: Andrew Morreale (CNL); Keith Scott (WorleyParsons)

15:40 - 16:00 HOW ARGENTINA SAVED THE C6 CONTAINMENT

N. G. Craik (retired from Canatom)

16:00 - 16:20 UPDATE OF SEVERE ACCIDENT MANAGEMENT GUIDELINES AT POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), S. Robertson (New Brunswick Power), D. J. Wilson (Atlantic Nuclear Inc.)

16:20 - 16:40 ASSESSMENT OF THERMALHYDRAULIC PHENOMENA FOR EXTERNAL WATER MAKE-UP

C. Harwood (CNSC), J. Baschuk (CNL)

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Session: 1B3 - Safety and Licensing (I) Paper Abstracts / Sommaires

15:40 - 16:00 - Montagu II

HOW ARGENTINA SAVED THE C6 CONTAINMENT

N. G. Craik (retired from Canatom)

In 1974, Argentine engineers observed that the design had not yet started on the passage from the Service Building (SB), through the Reactor Building (RB) Containment wall and into Irradiated Fuel Transfer Room (IFTR). The design pressure caused by Loss of Coolant Accident (LOCA) was greater than the head of water in the IFTR, so that the water in the IFTR would be blown out through the Fuel Transfer Canal (FTC) into the Service Building. The openings in the RB and IFTR would move differentially during a seismic event because these structures only shared the same base slab. The designers responded that it was intended to have a Containment Passage (CP) from the SB, though the RB and into the IFTR, and to incorporate flexible metallic bellows units at both ends of the proposed containment passage; at the IFTR and the RB Containment wall.

16:00 - 16:20 - Montagu II

UPDATE OF SEVERE ACCIDENT MANAGEMENT GUIDELINES AT POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), S. Robertson (New Brunswick Power), D. J. Wilson (Atlantic Nuclear Inc.)

In response to the events at Fukushima Dai’ichi, the CANDU Owners Group (COG) embarked on Joint Project JP4426 to update the overall framework for Severe Accident Management Guidelines (SAMG) to reflect lessons learned. This includes enhancements to consider SAMG in the shutdown/low power state, more extensive consideration of Spent (Irradiated) Fuel Bay (SFB) events and to address plant habitability issues. Point Lepreau is in the process of applying the COG methodologies in developing site-specific basis documents and revisions to SAM guidance documents. The paper will also describe SAMG for the Canister site, emergency procedure revisions to deal with extreme natural events and recommendations for evacuation of protective zones based on plant state criteria.

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16:20 - 16:40 - Montagu II

ASSESSMENT OF THERMALHYDRAULIC PHENOMENA FOR EXTERNAL WATER MAKE-UP

C. Harwood (CNSC), J. Baschuk (CNL)

Following the Fukushima Daiichi accident, Canadian NPP licensees implemented a number of changes, including additional provisions for water make-up to the reactor/boiler systems. The CNSC has placed a contract with CNL to model some of the make-up options, focusing on cooling via the boilers to prevent core damage. Such strategies have been credited with sustaining thermo-syphoning in the primary system and thus prolonging the available time for the operator to provide pumped make-up to the boilers or emergency coolant injection to the core, thereby maintaining decay heat removal. This paper presents results of CATHENA calculations of an extended loss of all electrical power in which the operator manually depressurizes the boilers by crash-cooling, thus allowing water to flow to the boilers by gravity from the deaerator tank. The rapid cooling of the boilers promotes thermo-syphoning flow in the primary heat transport system and results in a corresponding cool-down and depressurization of this system.

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1B4 - Communication15:40-16:40 - Montagu III

Co-Chairs: Philip Kompass (CNL); Matthew Dalzell (Sylvia Fedoruk Canadian Centre for Nuclear Innovation)

15:40 - 16:00 LESSONS LEARNT FROM FUKUSHIMA ACCIDENT – WHAT DID MCMASTER UNDERGRADUATE STUDENTS LEARN?

S. Nagasaki (McMaster University)

16:00 - 16:20 NuclearFACTS: PUBLIC ENGAGEMENT ABOUT THE IMPACTS OF NUCLEAR RESEARCH

M. Dalzell, N. Alexander, M. Main (Sylvia Fedoruk Canadian Centre for Nuclear Innovation)

16:20 - 16:40 INDUSTRY-UNIVERSITY COLLABORATION FOR RESEARCH AND EDUCATION

B. Shalaby, V. Snell, B. Rouben (UNENE)

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Session: 1B4 - CommunicationPaper Abstracts / Sommaires

15:40 - 16:00 - Montagu III

LESSONS LEARNT FROM FUKUSHIMA ACCIDENT – WHAT DID MCMASTER UNDERGRADUATE STUDENTS LEARN ?

S. Nagasaki (McMaster University)

Nuclear communities not only in Japan but also around the world learnt a lot of lessons from the Fukushima accident. The direct cause of the accident from the viewpoint of traditional engineering is clear, and as a result various measures have been implemented around the world. The accident also provides many insights into the relationship between traditional engineering and Japanese society. In this paper, the root causes of the accident were studied by applying a psychological model for evocation of an individual’s anxiety related to social affairs [1] to the discussions in an undergraduate course at McMaster University. In the last section, the challenges, which McMaster students considered Japanese nuclear community is now facing and Canadian nuclear community can contribute to in the future, are summarized.

16:00 - 16:20 - Montagu III

NuclearFACTS: PUBLIC ENGAGEMENT ABOUT THE IMPACTS OF NUCLEAR RESEARCH

M. Dalzell, N. Alexander, M. Main (Sylvia Fedoruk Canadian Centre for Nuclear Innovation)

The Forum for Accountability and Communities Talking nuclear Science – nuclearFACTS– is a cornerstone of the Sylvia Fedoruk Canadian Centre for Nuclear Innovation’s efforts to engage the people of Saskatchewan in evidence-based conversations about the impacts of the nuclear research, development and training activities supported by the Fedoruk Centre. The second annual nuclearFACTS public colloquium was held 20 November 2014, and featured the participation of 16 research projects. This paper discusses the continued development of the nuclearFACTS concept and its role in the Fedoruk Centre’s upstream engagement efforts.

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16:20 - 16:40 - Montagu III

INDUSTRY-UNIVERSITY COLLABORATION FOR RESEARCH AND EDUCATION

B. Shalaby, V. Snell, B. Rouben (UNENE)

University Network for Excellence in Nuclear Engineering also known as UNENE is a joint partnership between the nuclear industry and thirteen universities. UNENE has been legally registered as of 2002 as a not for profit organization. The establishment of this network was prompted by industry to address anticipated retirement of a large number of professionals from industry starting in early 2000 onwards and thus the loss of nuclear knowledge and experience within industry. UNENE was created to provide a sustainable supply of highly qualified personnel to industry, support nuclear research within various universities and provide a course based Master’s Degree in nuclear engineering to enhance the knowledge of young professionals within the industry in the science and technology of the CANDU nuclear power system. The paper describes the current UNENE, its research objectives, key outcomes of research programs to date and its contribution to industry needs in maintaining an economic and safe power plant performance of its nuclear fleet. The paper addresses achievements within the education program and the new 4-course diploma program recently introduced to enhance core expertise of young industry professionals. Also publications and national and international collaborations in various aspects of research have significantly contributed to Canada`s position in nuclear science and research worldwide. Such collaborations are also addressed.

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Student Poster Session and Wine-and-Cheese Reception17:30-19:30 - Marco Polo & Foyer

Chairs: Willy Cook (University of New Brunswick); Tracy Lapping (CNS)

PROLIFERATION RESISTANCE ASSESSMENT OF DIFFERENT FUEL CYCLES IN THE CANDU SYSTEM

X. Wang, A. Buijs, S. Nagasaki (McMaster University)

THE EFFECT OF IONIC STRENGTH ON THE ABSORPTION AND SPECIATION OF PALLADIUM

J. Riddoch, S. Nagasaki (McMaster University)

DEVELOPMENT OF A SIMPLE GAMMA RAY CAMERA USING HANDHELD SCINTILLATION DETECTORS

A. Miller, R. Machrafi (UOIT)

DEVELOPMENT OF A FUEL PERFORMANCE MODEL OF (TH,PU)O2 J. S. Bell, P. Chan (Royal Military College of Canada)

ERROR ANALYSIS OF SUPERCRITICAL WATER CORRELATIONS USING ATHLET SYSTEM CODE FOR LOW AND MODERATE MASS FLUX CASES

J. Samuel (UOIT)

NUCLEAR SECURITY REGULATORY FRAMEWORK ANALYSIS FOR SMALL MODULAR REACTORS IN CANADA AND ABROAD

A. Farah (UOIT)

HEAT LOSS ANALYSIS FOR A RE-ENTRANT SCWR FUEL-CHANNEL CONCEPT

F. Rafat (UOIT)

2D CFD MODELLING OF RADIOACTIVE PARTICLE RESUSPENSION Sharman Perera, Ed Waller, Ali Akhtar and Andrew Doxtator (UOIT)

REVISED NUMERICAL MODEL FOR F2 BUBBLE BREAKDOWN IN MOLTEN FLIBE AND ITS ECONOMICS IN THE FUEL CYCLE

K. Seto (UOIT)

HEAT TRANSFER ANALYSIS FOR THE APPLICATION OF SCWR PROCESS HEAT FOR THE THERMOCHEMICAL PRODUCTION OF HYDROGEN

J. C. Jouvin, I. Pioro (UOIT)

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HEAT-TRANSFER CHARACTERISTICS OF SUPERCRITICAL WATER FLOWING UPWARD IN BARE-TUBES

K. Sidawi (UOIT)

PULSED EDDY CURRENT RESPONSE TO MAGNETITE AT BROACH SUPPORTS IN STEAM GENERATORS

S. Mokros, J. Buck, R. Underhill (Royal Military College of Canada), J. Morelli (Queen’s University), T. Krause (Royal Military College of Canada)

PREDICTION OF HEAT TRANSFER IN A VERTICAL BARE TUBE UPWARD FLOW

R. Abdullah, V. Agranat, M. Malin, I. Pioro (UOIT)

DETERMINING THE EFFICACY OF NUCLEAR SECURITY THROUGH COMPUTER SIMULATION

N. Chornoboy, E. Waller (UOIT)

REGRESSION ANALYSIS OF PULSED EDDY CURRENT SIGNALS FOR INSPECTION OF STEAM GENERATOR TUBE SUPPORT STRUCTURES

J. Buck, P. R. Underhill, S. Mokros (Royal Military College of Canada), J. Morelli (Queen’s University), T. Krause (Royal Military College of Canada), V. Babber, B. Lepine (Canadian Nuclear Laboratories)

THE EFFECT OF WELD CHEMISTRY ON THE LIKELY PRIMARY WATER STRESS CORROSION CRACKING SUSCEPTIBILITY OF ALLOY 82 DISSIMILAR METAL WELDS

S. Persaud, S. Ramamurthy, R. Newman (University of Toronto)

COMPARISON STUDY ON AIR OXIDATION BEHAVIOR OF ADVANCED SUPER-ALLOYS IN ELEVATED TEMPERATURES

M. Sanayei, M. Nezakat, H. Akhiani, J. Szpunar (University of Saskatchewan)

PRESSURE-DROP ANALYSIS OF A RE-ENTRANT FUEL CHANNEL IN A PRESSURE-CHANNEL SUPERCRITICAL WATER-COOLED REACTOR

D. Kowalczyk, F. Rafat, M. Chauhan (UOIT)

A PRELIMINARY ASSESSMENT OF RADIATION EFFECTS ON AMERICAN FLAGFISH

M. Tzivaki, E. Waller (UOIT)

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MITIGATION OF END FLUX PEAKING IN CANDU FUEL BUNDLES USING NEUTRON ABSORBERS

D. Pierce, P. Chan (Royal Military College of Canada), W. Shen (Canadian Nuclear Safety Commisson)

NUCLEAR DATA SENSITIVITY AND UNCERTAINTY ANALYSIS FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR (SCWR) 64 – ELEMENT FRESH FUEL LATTICE CELL

A. Moghrabi, D. Novog (McMaster University)

CONTROL BLADE PATTERN OPTIMIZATION USING EVOLUTIONARY ALGORITHM FOR THE CANADIAN SCWR

F. Salaun, J. R. Sharpe, D. Hummel, D. Novog (McMaster University)

REACTION RATE PREDICTION IN THE SUPERCRITICAL REGION OF H + OH- ⇌ e(aq)- + H2O using μSR

T. Du, G. Liu, J. Beninger, K. Ghandi (Mount Allison)

AB INITIO INVESTIGATION OF CHLOROAQUALEAD (II) COMPLEXES AS POSSIBLE CORROSION PRODUCTS IN SUPER CRITICAL WATER COOLED REACTOR (SCWR)

D. Anzelj (Saint Mary’s Univeristy), C. Pye (Saint Mary’s Universty)

INVESTIGATION OF THE THERMAL STABILITY OF NdxScyZr1-x-yO2-δ INERT MATRIX FUEL MATERIALS

J. Hayes (University of Saskatchewan), M. Saoudi (Canadian Nuclear Laboratories), A. Grosvenor (University of Saskatchewan)

SEPARATION OF THE SECONDARY ELECTRONS FROM THE GAMMA RADIATION NEAR THE SURFACE OF AN ENCAPSULATED GAMMA SOURCE USING A MAGNETIC FIELD

E. Heritage, E. Waller (UOIT)

STUDY OF IRRADIATION INDUCED DEFECTS AND PHASE INSTABILITY IN ? PHASE OF ZR EXCEL ALLOY WITH IN-SITU HEAVY ION IRRADIATION

H. Yu, Z. Yao, M. A. Kirk, M. R. Daymond (Queen’s University)

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INFLUENCE OF ALKALI METAL OXIDES AND ALKALINE EARTH METAL OXIDES ON THE MITIGATION OF STRESS CORROSION CRACKING IN CANDU FUEL SHEATHING

J. Metzler, G. Ferrier, K. Farahani, P. Chan, E. Corcoran (Royal Military College of Canada)

MODELLING HYDROGEN PERMEATION IN A HYDROGEN EFFUSION PROBE FOR MONITORING CORROSION OF CARBON STEELS

P. Santiwiparat (University of New Brunswick), T. Rirksomboon (Chulalongkorn University), F. R. Steward, D. H. Lister, W. G. Cook (University of New Brunswick)

EXPERIMENTAL RESULTS SUPPORTING THE CONCEPT OF ONE-SIDED MUON TOMOGRAPHY

K. Boniface (McMaster University), G. Jonkmans (Canadian Nuclear Laboratories), A. Buijs (McMaster University), A. Erlandson, S. Livingstone (Canadian Nuclear Laboratories)

MODELLING THE LONG-TERM CORROSION BEHAVIOUR OF CANDIDATE ALLOYS FOR THE CANADIAN SCWR

G. Steeves, W. Cook (University of New Brunswick)

EXPERIMENTAL AND THERMODYNAMIC STUDIES OF BERYLLIUM REPLACEMENT MATERIALS FOR CANDU® BRAZED JOINTS

K. Potter, G. Ferrier, E. Corcoran (Royal Military College of Canada)

MONTE CARLO SIMULATIONS OF THE SLOWPOKE-2 REACTOR A. Tan, A. Buijs (McMaster University)

SENSING AND COLLECTING RADIOACTIVE MATERIALS AS A PROJECT TO TEACH ENGINEERING DESIGN

D. Drake, T. Majdi, J. Strack, A. Buijs (McMaster University)

DEVELOPMENT OF METHODOLOGY TO ASSESS APPLICATION OF PRACTICAL ELIMINATION FOR NUCLEAR POWER PLANTS

J. Jung, D. Sivekumar, S. Thambirasa (UOIT)

MONTE CARLO MODELING OF THE FASTSCAN WHOLE BODY COUNTER RESPONSE

H. Graham (UOIT)

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DESIGNING A COMPUTER CODE TO ESTIMATE THE COMMITTED DOSE EQUIVALENT TO INTERNAL ORGANS FOLLOWING THE INJECTION OF A RADIOPHARMACEUTICAL

Z. Keldani, R. Roman, S. Saadi (UOIT)

PROJECT MANAGEMENT LESSONS LEARNED FROM BUILDING THE WENDELSTEIN 7-X STELLERATOR FUSION RESEARCH REACTOR

M. Freire-Gormaly, A. Gittens, L. Zhang (University of Toronto)

CANADIAN SUPER CRITICAL WATER REACTOR: MODELING USING G4STORK

W. Ford (McMaster University)

MODELLING THE TRANSPORT OF CORROSION PRODUCTS AND RADIONUCLIDES IN THE CANDU PRIMARY HEAT TRANSPORT SYSTEM

O. Palazhchenko, D. Lister (University of New Brunswick)

DOSE MEASUREMENT ABOARD BIOSATELLITE BION-M #1 (AUTOCAD IMPLEMENTATION INTO MCNPX)

P. Dolloso, A. Miller, R. Machrafi (UOIT), V. Shurshakov, S. Khulapko, O. Ivanova (Institute of Biomedical Problems, Moscow, Russian Federation)

A NEW METHOD TO CORRELATE HEAT TRANSFER DATA FOR SUPERCRITICAL FLUIDS IN FORCED CONVECTIVE REGIME

E. Saltanov, G. Harvel, I. Pioro (UOIT)

TUESDAY JUNE 2 / MARDI 2 JUINTUESDAYTUESDAYM

ARDITUESDAYMARDI

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TUESDAY JUNE 2 / MARDI 2 JUIN

Breakfast for Speakers & Chairs of the Day07:00-07:45 - Belleisle I & II


2A1 - Panel Discussion on International Developments in Used Nuclear Fuel Repository Programs

08:00-09:40 - LoyalistChair: Elena Mantagaris

(Nuclear Waste Management Organization)

08:00 - 08:20 CANADA’S PLAN FOR THE LONG-TERM MANAGEMENT OF USED NUCLEAR FUEL

K. Shaver (Nuclear Waste Management Organization)

08:20 - 08:40 INTERNATIONAL OVERVIEW ON RADIOACTIVE WASTE MANAGEMENT

M. Siemann (NEA/OECD)

08:40 - 09:00 THE FRENCH GEOLOGICAL DISPOSAL PROJECT CIGEO

G. Ouzounian (ANDRA)

09:00 - 09:20 AN UPDATE OF THE U.S. PROGRAM FOR THE MANAGEMENT OF USED NUCLEAR FUEL

T. Isaacs (US Blue Ribbon Commission)

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2A2 - Safety and Security 08:00-09:40 - Montagu I

Co-Chairs: Matthew Daley (CNL); Shinya Nagasaki (McMaster University)

08:00 - 08:20 OPERATING NUCLEAR POWER STATIONS IN A REGULATED CYBER SECURITY ENVIRONMENT: A ROADMAP FOR SUCCESS

E. Dorman (AREVA Inc.)

08:20 - 08:40 EFFECT OF HIGH FREQUENCY CONTENT OF UNIFORM HAZARD RESPONSE SPECTRA ON NUCLEAR POWER PLANT STRUCTURES, SYSTEMS AND COMPONENTS

A. Usmani (Amec Foster Wheeler), P. Baughman (Paul D. Baughman Consulting)

08:40 - 09:00 FIRE ALARM DETECTION IN HIGH-CEILING ROOMS

R. Brewer, L. Morrison (PLC Fire Safety Solutions)

09:00 - 09:20 CYBER SECURITY - COMPLIANCE TO THE NEW CSA 290.7 STANDARD

M. Daley, R. Doucet, M. Echlin, M. MacDonald, V. Mihaylov, J. Sijs, D. Trask (CNL)

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Session: 2A2 - Safety and Security Paper Abstracts / Sommaires

08:00 - 08:20 - Montagu I

OPERATING NUCLEAR POWER STATIONS IN A REGULATED CYBER SECURITY ENVIRONMENT: A ROADMAP FOR SUCCESS

E. Dorman (AREVA Inc.)

The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NRC. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility.

The Program is designed to protect critical digital assets (CDAs) by applying and maintaining defense-in-depth protective strategies to ensure the capability to detect, respond to, and recover from cyber-attacks. The Program references NEI 08-09 R. 6, the Nuclear Energy Institute Template that provides guidance for applying Cyber Security controls derived from NIST 800-53/82 and slightly modified to fit the nuclear environment. Many mature processes are in place at nuclear facilities in response to numerous regulations implemented over the past 30 years. Many of these processes such as the Physical Security Program offer protections that are leveraged to protect the functions of critical digital assets from unauthorized physical access. Other processes and technology such as engineering design control, work management and pre-job briefs, control of portable media and mobile devices, and deterministically segregated networks protect critical digital assets. By leveraging the regulated nuclear environment, integrating NIST type Cyber Security controls, and prudently deploying technology the Cyber Security posture of operating nuclear facilities supports on-demand base load electricity 24/7 with capacity factors exceeding 85%. This paper is designed to provide a glimpse into Cyber Security Programs that support safe operation and reliability in the regulated nuclear environment while supporting the on-demand base load electricity production 24/7.

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08:20 - 08:40 - Montagu I

EFFECT OF HIGH FREQUENCY CONTENT OF UNIFORM HAZARD RESPONSE SPECTRA ON NUCLEAR POWER PLANT STRUCTURES, SYSTEMS AND COMPONENTS

A. Usmani (Amec Foster Wheeler), P. Baughman (Paul D. Baughman Consulting)

The Uniform Hazard Spectrum (UHS) is developed from a probabilistic seismic hazard assessment and represents a response spectrum for which the amplitude at each frequency has a specified and uniform (equal) probability of exceedance. The high spectral acceleration at high frequencies in the UHS can result mainly from small non-damaging low energy earthquakes. Historically Canadian and U.S. nuclear power plants have been designed using the standard shape spectrum given in CSA N289.3 or USNRC Regulatory Guide 1.60, which have maximum spectral accelerations in the lower (2-10 Hz.) frequency range. The impact of the high frequency content of UHS on the nuclear power plant SSCs is required to be assessed.

This paper briefly describes the methodologies used for screening and evaluation of the effects of UHS high frequency content on the nuclear power SSCs that have been designed using the CSA N289.3 standard shape spectrum.

08:40 - 09:00 - Montagu I

FIRE ALARM DETECTION IN HIGH-CEILING ROOMS

R. Brewer, L. Morrison (PLC Fire Safety Solutions)

For life extension of nuclear power plants, new codes must often be applied. For fire alarm systems, these codes can result in the addition of fire detectors in locations where none had previously been required. In rooms with ceilings at typical heights, designing detection is generally not problematic. It can, however, be more challenging to design fire alarm detection in spaces with high ceilings. In these environments, fire alarm systems should be designed considering the effects that high ceilings can have on the dynamics of a fire. If not, they can be ineffective, and result in significant cost for the installation and maintenance of a system that does not meet its design objectives.

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09:00 - 09:20 - Montagu I

CYBER SECURITY - COMPLIANCE TO THE NEW CSA 290.7 STANDARD

M. Daley, R. Doucet, M. Echlin, M. MacDonald, V. Mihaylov, J. Sijs, D. Trask (CNL)

Since 2008, the Canadian Nuclear Safety Commission (CNSC), similar to regulators of other critical industries, has requested their licensees to implement cyber security programs and conduct self-assessments without the benefit of an industry specific cyber security standard that provides common metrics for coverage and effectiveness of their programs. However, for the nuclear industry, a new CSA standard 290.7 entitled “Cyber security for nuclear power plants and small reactor facilities” [1], released in December 2014, will have the CNSC looking to facility operators to be compliant to the new standard.

This paper will discuss initiatives at Canadian Nuclear Laboratories to develop of a suite of tools, techniques, and best practices that can be used by the regulator and industry for assessing compliance and effectiveness of cyber security technology and implementations.

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2A3 - Instrumentation and Control08:00-09:40 - Montagu II

Co-Chairs: Mohinder Grover (M.S. Grover & Associates); Aman Usmani (Amec Foster Wheeler)

08:00 - 08:20 THE ROLE OF AUTOMATED TESTING AND LOGGING TOOLS IN FUEL HANDLING I&C REFURBISHMENT: BRUCE A NGS FH PROTECTIVE REPLACEMENT

J. Dalby, Y. Mackwood, W. Volk (GE Hitachi Nuclear Energy Canada Inc.), W. Yu (Bruce Power)

08:20 - 08:40 LIMERICK BWR TURBINE CONTROL AND PROTECTION SYSTEM UPGRADE SUCCESS

C. Tang, T. Pietryka, P. Federico (Westinghouse Electric Company)

08:40 - 09:00 DEVELOPMENT, APPLICATION AND LICENSING OF FPGA BASED SAFETY SYSTEMS

T. Tuite, J. Carvajal (Westinghouse Electric Company)

09:00 - 09:20 POINT LEPREAU INSTRUMENT AND EQUIPMENT SURVIVABILITY ASSESSMENT DURING SEVERE ACCIDENT CONDITIONS

D. Mullin (NB Power, Point Lepreau Generating Station)

09:20 - 09:40 OVERVIEW OF MONITORING APPLICATIONS FOR RETROFIT AND NEW-BUILD NPP PROJECTS

V. Thomas, C. Black (Westinghouse Electric Company)

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Session: 2A3 - Instrumentation and ControlPaper Abstracts / Sommaires

08:00 - 08:20 - Montagu II

THE ROLE OF AUTOMATED TESTING AND LOGGING TOOLS IN FUEL HANDLING I&C REFURBISHMENT: BRUCE A NGS FH PROTECTIVE REPLACEMENT

J. Dalby, Y. Mackwood, W. Volk (GE Hitachi Nuclear Energy Canada Inc.), W. Yu (Bruce Power)

The replacement and upgrade of nuclear-related I&C systems forms an important part of the refurbishment and life extension of the CANDU fleet. Replacement of the DEC PDP-based fuel handling Protective computer at the Bruce A NGS has brought with it challenges in both design reimplementation, and in ensuring a smooth path through installation and commissioning. In order to achieve success, innovative approaches to in-field data logging and automated testing equipment for PLCs were needed. GEH-C’s Automated Software Test Equipment and datalogger (ASTE/d) has been a key tool in ensuring verification and validation of replacement designs, test repeatability, and enhanced coverage, while contributing to project cost and schedule adherence.

08:20 - 08:40 - Kennebecasis I

LIMERICK BWR TURBINE CONTROL AND PROTECTION SYSTEM UPGRADE SUCCESS

C. Tang, T. Pietryka, P. Federico (Westinghouse Electric Company)

Westinghouse and Exelon have successfully implemented a digital electro-hydraulic control (DEHC) at Limerick BWR Unit 1 Station to perform the turbine control, protection and reactor pressure functions. The DEHC replaces analog controls and addressed system performance, obsolescence and reliability. This was a first-of-a-kind application for control and protection of the main turbine and BWR pressure control for the distributed control system utilized. The demolition of analog equipment, main control room and front standard modifications, and acceptance testing were completed on schedule during the normal 2014 outage. Key aspects of the project that facilitated this success will be discussed and presented.

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DEVELOPMENT, APPLICATION AND LICENSING OF FPGA BASED SAFETY SYSTEMS

T. Tuite, J. Carvajal (Westinghouse Electric Company)

Westinghouse has developed the Advanced Logic System platform® (ALS®). The ALS platform was recently approved by the US NRC. In addition, ALS was successfully installed and declared operational as a Thermocouple/Core Cooling Monitor upgrade at the Wolf Creek Generating Station. The ALS has also been installed at the AP1000 Sanmen and Haiyang unit sites as the Diverse Actuation System. The ALS platform is based on FPGA technology. FPGA safety system designs are simpler than comparable CPU based system designs in that they do not require an Operating System or instruction set. The ALS platform provides inherent diversity in redundant cores and diverse core designs. In addition, the ALS provides extensive self testing and diagnostics which allows for extension of plant surveillance intervals.


POINT LEPREAU INSTRUMENT AND EQUIPMENT SURVIVABILITY ASSESSMENT DURING SEVERE ACCIDENT CONDITIONS


Instrument and equipment survivability during severe accidents has always been recognized as an important consideration in assessing response capability. However, events during the 2011 Fukushima Dai’ichi accident have placed renewed focus on ensuring critical instrument and equipment is capable of performing its function during a severe accident. NB Power has performed a survivability assessment following the COG JP-4426 methodology to evaluate the capability of equipment and instrumentation used during a severe accident to achieve a controlled, stable state after core damage under the consequential unique and harsh containment environment. This paper describes the evaluation, its results and planned next steps.

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OVERVIEW OF MONITORING APPLICATIONS FOR RETROFIT AND NEW-BUILD NPP PROJECTS

V. Thomas, C. Black (Westinghouse Electric Company)

Westinghouse has provided digital I&C upgrade systems to the fleet of nuclear power plants worldwide from the earliest introduction of such technology to power generation, covering a complete range of applications including systems for protection, control, information, & monitoring. In this context, plant computer and vibration/diagnostic systems have been integral to existing plant retrofits as well as new-build (e.g. AP1000® plants). Westinghouse has positioned a set of integrated technologies to facilitate increased efficiency and effectiveness of system engineers relative to maintaining a high level of equipment readiness and reliability by leveraging I&C technology. This presentation provides an overview survey of such technologies and product applications.

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2A4 - Advanced Reactor Designs08:00-09:20 - Montagu III

Co-Chairs: Michael Soulard (Candu Energy Inc); Constantin Banica (Ontario Power Generation)

08:00-08:20 POWER FLATTENING AND REACTIVITY SUPPRESSION STRATEGIES FOR THE CANADIAN SUPERCRITICAL WATER REACTOR CONCEPT

M. McDonald, A. Colton, J. Pencer (Canadian Nuclear Laboratories)

08:20-08:40 A BENCHMARK COMPARISON OF THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR (SCWR) 64-ELEMENT FUEL LATTICE CELL PARAMETERS USING VARIOUS COMPUTER CODES

J. Sharpe, F. Salaun, D. Hummel, A. Moghrabi (McMaster University), M. Nowak (McMaster University; Institut National Polytechnique de Grenoble (Phelma)), J. Pencer (McMaster University, Canadian Nuclear Laboratories), D. Novog, A. Buijs (McMaster University)

08:40-09:00 STARCORE NUCLEAR GENERATION IV HTGR

M. K. Yates (StarCore Nuclear), F. Shahrokhi (AREVA), D. A. Poole, L. D. Eskin (StarCore Nuclear)

09:00-09:20 LEADIR-PS: PROVIDING UNPRECEDENTED SMR SAFETY AND ECONOMICS

R. Hart (Northern Nuclear Industries Incorporated)

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Session: 2A4 - Advanced Reactor DesignsPaper Abstracts / Sommaires

08:00-08:20 - Montagu III

POWER FLATTENING AND REACTIVITY SUPPRESSION STRATEGIES FOR THE CANADIAN SUPERCRITICAL WATER REACTOR CONCEPT

M. McDonald, A. Colton (CNL), J. Pencer (McMaster University, Canadian Nuclear Laboratories)

The Canadian supercritical water-cooled reactor (SCWR) is a conceptual heavy water moderated, supercritical light water cooled pressure tube reactor. In contrast to current heavy water power reactors, the Canadian SCWR will be a batch fuelled reactor. Associated with batch fuelling is a large beginning-of-cycle excess reactivity. Furthermore, radial power peaking arising as a consequence of batch refuelling must be mitigated in some way. In this paper, burnable neutron absorber (BNA) added to fuel and absorbing rods inserted into the core are considered for reactivity management and power flattening. A combination of approaches appears adequate to reduce the core radial power peaking, while also providing reactivity suppression.

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08:20-08:40 - Montagu II

A BENCHMARK COMPARISON OF THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR (SCWR) 64-ELEMENT FUEL LATTICE CELL PARAMETERS USING VARIOUS COMPUTER CODES

J. Sharpe, F. Salaun, D. Hummel, A. Moghrabi (McMaster University), M. Nowak (McMaster University; Institut National Polytechnique de Grenoble (Phelma)), J. Pencer (McMaster University, Canadian Nuclear Laboratories), D. Novog, A. Buijs (McMaster University)

Discrepancies in key lattice physics parameters have been observed between various deterministic (e.g. DRAGON and WIMS-AECL) and stochastic (MCNP, KENO) neutron transport codes in modeling previous versions of the Canadian SCWR lattice cell. Further, inconsistencies in these parameters have also been observed when using different nuclear data libraries. In this work, the predictions of k∞, various reactivity coefficients, and relative ring-averaged pin powers have been re-evaluated using these codes and libraries with the most recent 64-element fuel assembly geometry. A benchmark problem has been defined to quantify the dissimilarities between code results for a number of responses along the fuel channel under prescribed hot full power (HFP), hot zero power (HZP) and cold zero power (CZP) conditions and at several fuel burnups (0, 25 and 50 MW·d·kg-1 [HM]). Results from deterministic (TRITON, DRAGON) and stochastic codes (MCNP6, KENO V.a and KENO-VI) are presented.

08:40-09:00 - Montagu II

STARCORE NUCLEAR GENERATION IV HTGR

M. K. Yates (StarCore Nuclear), F. Shahrokhi (AREVA), D. Poole, L. Eskin (StarCore Nuclear)

StarCore Nuclear (StarCore) is developing a High Temperature Gas Cooled Reactor using TRISO fuel, prismatic graphite blocks and a helium primary loop. The design is currently evolving, with the intent of completing the conceptual design and submitting it to the Canadian Nuclear Safety Commission (CNSC) as part of a Vendor Design Review within one year. The paper will focus on the status and plans for the design of the reactor plant.

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09:00-09:20 - Montagu II

LEADIR-PS: PROVIDING UNPRECEDENTED SMR SAFETY AND ECONOMICS

R. Hart (Northern Nuclear Industries Incorporated)

Northern Nuclear Industries Incorporated is developing Small Modular Reactors (SMRs) called LEADIR-PS, an acronym for LEAD-cooled Integral Reactor-Passively Safe. LEADIR-PS integrates proven technologies including TRISO fuel, Pebble Bed core and graphite moderator, with molten lead coolant in an integral pool type reactor configuration to achieve unprecedented safety and economics. Plants under development are LEADIR-PS100 producing 100 MWth and LEADIR-PS300 producing 300 MWth that are focused on serving the energy demands of areas with a small electrical grid and/or process heat applications. A plant consisting of six LEADIR-PS300 reactor modules serving a common turbine-generator, called the LEADIR-PS Six-Pack, is focused on serving areas with higher energy demands and a robust electricity grid.

In response to market requests, LEADIR-PS30 (30 MWth) has been defined, avariation of LEADIR-PS100. Work to date is limited to defining the core.

The Gen IV+ LEADIR-PS plants are inherently/passively safe. There is no potential for a Loss Of Coolant Accident, a reactivity transient without shutdown, or a loss of heat sink. No active systems or operator actions are required to assure safety. The unprecedented safety of LEADIR-PS reactors avoids large exclusion radius and demanding evacuation plan requirements. LEADIR-PS, with steam conditions of 370 oC and 12 MPa can serve over 85% of the world’s non-transportation process heat demands. In Canada, the electricity and process heat demands, ranging from those of remote communities and the oil sands to densely populated areas can be served by LEADIR-PS

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2B1 - WMD - Deep Geological Repository Packaging 10:00-12:00 - Loyalist

Chairs: Chris Hatton, Derek Wilson, (Nuclear Waste Management Organization)

10:00 - 10:20 DEVELOPMENT OF THE CANADIAN USED FUEL REPOSITORY ENGINEERED BARRIER SYSTEM

C. Hatton (Nuclear Waste Management Organization)

10:20 - 10:40 HYBRID LASER ARC WELDING OF A USED FUEL CONTAINER

C. Boyle (Nuclear Waste Management Organization), P. Martel (Novika Solutions)

10:40 - 11:00 ELECTRODEPOSITED COPPER COATINGS FOR USED FUEL CONTAINERS

P. Keech (Nuclear Waste Management Organization), P. Lin, N. Mahalanobis (Integran Technologies Inc)

11:00 - 11:20 COLD SPRAY COPPER COATINGS FOR USED FUEL CONTAINERS

P. Keech (Nuclear Waste Management Organization), P. Vo, D. Poirier, J. G. Legoux (National Research Council)

11:20 - 11:40 USED FUEL PACKING PLANT FOR CANDU FUEL

I. Menzies, B. Thayer (ATS Automation), A. Murchison (Nuclear Waste Management Organization), N. Bains (ATS Automation)

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Session: 2B1 - WMD - Deep Geological Repository Packaging

Paper Abstracts / Sommaires

10:00 - 10:20 - Loyalist

DEVELOPMENT OF THE CANADIAN USED FUEL REPOSITORY ENGINEERED BARRIER SYSTEM


The Nuclear Waste Management Organization (NWMO) is responsible for the implementation of Adaptive Phased Management (APM), the federally-approved plan for the safe long-term management of Canada’s used nuclear fuel. Under the APM plan, used nuclear fuel will ultimately be placed within a deep geological repository in a suitable rock formation.

In implementing APM, the NWMO is committed to ensure consistency with international best practices in the development of its repository system, including any advances in technology.

In 2012, the NWMO undertook an optimization study to look at both the design and manufacture of its engineered barriers. This study looked at current technologies for the design and manufacture of used fuel containers, placement technologies, repository design, and buffer and sealing systems, while taking into consideration the state of the art worldwide in repository design and acceptance.

The result of that study is the current Canadian engineered barrier system, consisting of a 2.7 tonne used fuel container with a carbon-steel core, copper-coated surface and welded spherical heads. The used fuel container is encapsulated in a bentonite buffer box at the surface and then transferred underground. Once underground, the used fuel is placed into a repository room which is cut into the rock using traditional drill-and-blast technologies.

This paper explains the logic for the selection of the container and sealing system design and the development of innovative technologies for their manufacture including the use of laser welding, cold spray and pulsed-electrodeposition copper coating for the manufacture of the used fuel container, isostatic presses for the production of the one-piece bentonite blocks, and slip-skid technologies for placement into the repository.

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10:20 - 10:40 - Loyalist

HYBRID LASER ARC WELDING OF A USED FUEL CONTAINER

C. Boyle (Nuclear Waste Management Organization), P. Martel (Novika Solutions)

The Nuclear Waste Management Organization (NWMO) has designed a novel Used Fuel Container (UFC) optimized for CANDU used nuclear fuel. The Mark II container is constructed of nuclear grade pipe for the body and capped with hemi-spherical heads. The head-to-shell joint fit-up features an integral backing designed for external pressure, eliminating the need for a full penetration closure weld. The NWMO and Novika Solutions have developed a partial penetration, single pass Hybrid Laser Arc Weld (HLAW) closure welding process requiring no post-weld heat treatment. This paper will discuss the joint design, HLAW process, associated welding equipment, and prototype container fabrication.

10:40 - 11:00 - Loyalist

ELECTRODEPOSITED COPPER COATINGS FOR USED FUEL CONTAINERS

P. Keech (Nuclear Waste Management Organization), P. Lin, N. Mahalanobis (Integran Technologies Inc)

Recently, copper coating of used fuel containers (UFCs) has been an area of research at the Nuclear Waste Management Organization, as copper offers a means of protecting steel UFCs from corrosion within a deep geological repository. The design is based on the application of a high purity copper coating directly to the surface of the UFC structural core. In the proposed fabrication sequence, vessel components would be delivered to the Used Fuel Packing Plant pre-coated with copper. Electrodeposition has been identified as a particularly adaptable method for this purpose; this paper will present applied research in this area.

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11:00 - 11:20 - Loyalist

COLD SPRAY COPPER COATINGS FOR USED FUEL CONTAINERS

P. Keech (Nuclear Waste Management Organization), P. Vo, D. Poirier, J. G. Legoux (National Research Council)

Recently, the Nuclear Waste Management Organization has been developing copper coatings as a method of protecting steel used fuel containers (UFCs) from corrosion within a deep geological repository. The corrosion barrier design is based on the application of a copper coating bonded directly to the exterior surface of the UFC structural core. Copper coating technologies amendable to supply of pre-coated UFC vessel components and application to the weld zone following UFC closure within the radiological environment have been investigated. Copper cold spray has been assessed for both operations; this paper outlines the research and development to date of this technique.

11:20 - 11:40 - Loyalist

USED FUEL PACKING PLANT FOR CANDU FUEL

I. Menzies, B. Thayer (ATS Automation), A. Murchison (Nuclear Waste Management Organization), N. Bains (ATS Automation)

Large forgings have been selected to containerize Light Water Reactor used nuclear fuel. CANDU fuel, which is significantly smaller in size, allows novel approaches for containerization. For example, by utilizing commercially available extruded ASME pipe a conceptual design of a Used Fuel Packing Plant for containerization of used CANDU fuel in a long lived metallic container has been developed. The design adopts a modular approach with multiple independent work cells to transfer and containerize the used fuel. Based on current technologies and concepts from proven industrial systems, the Used Fuel Packing Plant can assemble twelve used fuel containers per day considering conservative levels of process availability.

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2B2 - Reactor Physics10:00-12:00 - Montagu I

Co-Chairs: Michael McDonald (CNL); Adriaan Buijs (McMaster University)

10:00 - 10:20 EFFECT OF DOWNGRADED MODERATOR PURITY ON LATTICE REACTIVITY AND COOLANT VOID REACTIVITY FOR A LEU LATTICE IN THE ZED-2 REACTOR

M. Zeller, J. Chow (CNL)

10:20 - 10:40 EC6 DESIGN IMPROVEMENTS AND CONFIRMATORY TESTING

S. Yu, L. Drennan, M. Soulard (Candu Energy Inc.)

10:40 - 11:00 ADJUSTER ROD AGING IN DARLINGTON’S CANDU REACTORS: BEHAVIOUR, MEASUREMENT AND IMPLICATIONS FOR OPERATION

C. Banica, A. Sullivan (Ontario Power Generation)

11:00 - 11:20 MEASUREMENT AND ANALYSIS FOR DETERMINATION OF POWER COEFFICIENT OF REACTIVITY OF AN OPERATING CANDU6

J. Kim (KAIST), Y. Kim (Department of Nuclear and Quantum Engineering, KAIST), K. Kim (Korea Hydro & Nuclear Power Co.)

11:20 - 11:40 CANDU6 PCR EVALUATION WITH A DETAILED 3-D MONTE CARLO ANALYSIS

M. Abdul Motalab, W. Kim (Korea Advanced Institute of Science and Technology), Y. Kim (Department of Nuclear and Quantum Engineering, KAIST)

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Session: 2B2 - Reactor PhysicsPaper Abstracts / Sommaires

10:00 - 10:20 - Montagu I

EFFECT OF DOWNGRADED MODERATOR PURITY ON LATTICE REACTIVITY AND COOLANT VOID REACTIVITY FOR A LEU LATTICE IN THE ZED-2 REACTOR

M. Zeller, J. Chow (CNL)

ZED-2 criticality measurements have been compiled using a lattice comprising Low Enriched Uranium (LEU) fuel assemblies. The data obtained are to determine the effect of down-graded moderator purity on lattice reactivity and Coolant Void Reactivity (CVR) for the test lattice. The data span moderator purities ranging from 99.882 to 98.519 weight % D2O. Since the fuel assemblies comprise LEU, the measurements did not require changing the lattice configuration over the range of purities studied. These data therefore provide unique applicability to address the reactor physics phenomenon Moderator-Purity-Change-Induced Reactivity and its impact on Coolant Void Reactivity (CVR).

An analysis was performed using the Monte Carlo code MCNP5 (v1.40) employing nuclear data derived from the ENDF/B-VII.0 evaluation. Reactivity coefficients are determined from the experimental data and compared to code predictions. The comparison indicates that there are suspected errors in the nuclear-data library regarding the cross sections for hydrogen in heavy water.

10:20 - 10:40 - Montagu I

EC6 DESIGN IMPROVEMENTS AND CONFIRMATORY TESTING

S. Yu, L. Drennan, M. Soulard (Candu Energy Inc.)

The EC6 confirmatory testing program is a fundamental component of the EC6 development project to confirm design enhancements from the CANDU 6 Reference Qinshan plant. The confirmatory testing and analysis activities planned focuses on the testing needed to support the application for a construction licence. The program comprises work planned and executed by Candu Energy Inc. and work that has been completed to ensure EC6 product readiness for new build or refurbishment project implementation.

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The key objectives of the testing program are:

• Verification of design changes.

• Validation of computer codes, assumptions and models.

• Demonstration and performance testing of new control computers and control centre equipment.

This paper provides a description of the completed testing program for key EC6 design improved features or equipment particularly those for reactor core components:

- Pressure Tubes and rolled joints

- Calandria Tubes and rolled joints

- Fuel Channel Annulus Spacer

- Shutoff units in Shutdown Systems #1

10:40 - 11:00 - Montagu I

ADJUSTER ROD AGING IN DARLINGTON’S CANDU REACTORS: BEHAVIOUR, MEASUREMENT AND IMPLICATIONS FOR OPERATION

C. Banica, A. Sullivan (Ontario Power Generation)

Presented are the simulation methodology and the results of reactivity worth measurements performed on adjuster rods in an equilibrium Darlington (large CANDU) core. Simulation had predicted the effect of neutron irradiation on device properties for adjuster rods of different construction and in-core residence times. The expected difference in the rate of irradiation-induced reactivity worth loss in rods containing titanium versus all stainless steel has been confirmed by comparing measured reactivity values for adjuster rods that differ in material construction and in-core service times. Also discussed are the method for conducting the measurements, and the accuracy of pre-simulation results.

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11:00 - 11:20 - Montagu I

MEASUREMENT AND ANALYSIS FOR DETERMINATION OF POWER COEFFICIENT OF REACTIVITY OF AN OPERATING CANDU6

J. Kim (KAIST), Y. Kim (Department of Nuclear and Quantum Engineering, KAIST), K. Kim (Korea Hydro & Nuclear Power Co.)

The power coefficient of reactivity (PCR) needs to be negative to achieve the inherent safety of a reactor, but the PCR of CANDU-6 has been evaluated to be positive in recent studies. In this circumstances, an experiment was performed at a CANDU-6 reactor in Korea to measure the PCR of CANDU-6. Based on the measurement data, the PCR was evaluated by a newly proposed methodology which requires several estimations of reactivity variation due to liquid zone controllers, xenon, etc. Consequently, the PCR of CANDU-6 was evaluated to be about 0.5 pcm/%Power which is slightly smaller than the latest official value, 1.7 pcm/%Power.

11:20 - 11:40 - Montagu I

CANDU6 PCR EVALUATION WITH A DETAILED 3-D MONTE CARLO ANALYSIS

M. Abdul Motalab, W. Kim (Korea Advanced Institute of Science and Technology), Y. Kim (Department of Nuclear and Quantum Engineering, KAIST)

In the original CANDU6 design, the PCR was evaluated to be clearly negative. However, the latest physics design tool predicts that PCR is slightly positive for a wide range of reactor power. In this work, the CANDU6 PCR is re-evaluated by a detailed 3-D CANDU6 core model using Monte Carlo code Serpent2 with considering two thermal hydraulic models, at design and operating condition. The Doppler broadening rejection correction method was implemented in the Serpent2 code to take into account thermal motion of uranium nucleus. It is found that the CANDU6 PCR can be clearly negative at low power range for both design and operating conditions.

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2B3 - Chemistry and Materials10:00-11:40 - Montagu II

Co-Chairs: Ashok Khanna (Indian Institute of Technology Kanpur); John Roberts (JGRchem.inc)

10:00 - 10:20 RADIATION CHEMISTRY IN SCWR G. Liu (Mount Allison University Department of

Physics), K. Ghandi (Mount Allison University)

10:20 - 10:40 INFLUENCE OF ALKALI METAL OXIDES AND ALKALINE EARTH METAL OXIDES ON THE MITIGATION OF STRESS CORROSION CRACKING IN CANDU FUEL SHEATHING

J. Metzler, G. A. Ferrier, K. Farahani, P. K. Chan, E. C. Corcoran (Royal Military College of Canada)

10:40 - 11:00 ASSESSMENT OF ALTERNATE ION EXCHANGE RESINS FOR IMPROVED ANTIMONY REMOVAL FROM THE PRIMARY HEAT TRANSPORT SYSTEM

R. Burany, S. Suryanarayan, A. Husain (Kinectrics)

11:00 - 11:20 SPECIFIC HEAT OF ZR-2.5NB PRESSURE TUBE MATERIAL MEASURED BY DIFFERENTIAL SCANNING CALORIMETRY (DSC)

R. W. L. Fong, P. Neal (CNL), F. Fazeli, M. Aniolek (CanmetMATERIALS), S. Gezgin (NETZSCH-Gerätebau GmbH)

11:20 - 11:40 THERMAL EXPANSION ANISOTROPY OF ZR-2.5NB PRESSURE TUBE MATERIAL ON HEATING TO 1100°C

R. W. L. Fong (CNL), F. Fazeli, T. Smith (CanmetMATERIALS)

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Session: 2B3 - Chemistry and MaterialsPaper Abstracts / Sommaires

10:00 - 10:20 - Montagu II

RADIATION CHEMISTRY IN SCWR

G. Liu (Mount Allison University Department of Physics), K. Ghandi (Mount Allison University)

In 2002, Ghandi and co-workers proposed a model that includes an efficiency factor to account for the “cage effect”. This model reproduces the plateau observed in available experimental data. Our group is working on reviewing all the reactions considered in the report submitted by Atomic Energy of Canada Limited in 2009 based on the cage effect model, in order to provide recommendations for the values of rate constants to use in modeling of water radiolysis reactions past the critical point. In this paper, we will be focusing on the very fast reactions that are diffusion controlled past the critical point.

10:20 - 10:40 - Montagu II

INFLUENCE OF ALKALI METAL OXIDES AND ALKALINE EARTH METAL OXIDES ON THE MITIGATION OF STRESS CORROSION CRACKING IN CANDU FUEL SHEATHING

J. Metzler, G. A. Ferrier, K. Farahani, P. K. Chan, E. C. Corcoran (Royal Military College of Canada)

This work investigates strategies to mitigate stress corrosion cracking (SCC) in Zircaloy-4 sheathing materials. The CANLUB coatings currently used in CANDU reactors contain both alkali metal and alkaline earth metal impurities, which can exist as oxides (e.g., Na2O and CaO). It is believed that when the corrosive fission product iodine reacts with these oxides, the iodine can be sequestered through the formation of an iodide (e.g.,NaI and CaI2). The subsequent O2 release may repair cracks in the protective ZrO2 layer on the sheathing, shielding the Zircaloy-4 sheathing from further corrosive fission product attack. For this investigation, O2 gas, Na2O, and CaO were separately introduced into an environment wherein slotted Zircaloy-4 rings endure mechanical stresses in iodine vapour at high temperatures. Controlled additions of O2 gas created a slight reduction in the corrosive attack on Zircaloy-4 sheathing, while the inclusion of Na2O and CaO lead to greater reductions.

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10:40 - 11:00 - Montagu II

ASSESSMENT OF ALTERNATE ION EXCHANGE RESINS FOR IMPROVED ANTIMONY REMOVAL FROM THE PRIMARY HEAT TRANSPORT SYSTEM

R. Burany, S. Suryanarayan, A. Husain (Kinectrics)

Radiation fields around the CANDU heat transport system are a major contributor to worker dose during inspection, maintenance and refurbishment activities. While Co-60 is typically the dominant contributor to radiation fields in CANDU reactors, Sb-124, an activation product of antimony, is also a significant contributor, accounting for 5-20% of the radiation fields. The goal of this research project was to investigate resins for improved removal of antimony under both oxidizing and reducing conditions.Several candidate resins were tested and shortlisted through a sequence of iterative testing. The results of the laboratory testing have identified potential candidates for improved antimony removal. Further testing is required to ensure compatibility with existing station resin specifications.

11:00 - 11:20 - Montagu II

SPECIFIC HEAT OF ZR-2.5NB PRESSURE TUBE MATERIAL MEASURED BY DIFFERENTIAL SCANNING CALORIMETRY (DSC)

R. W. L. Fong, P. Neal (CNL), F. Fazeli, M. Aniolek (CanmetMATERIALS), S. Gezgin (NETZSCH-Gerätebau GmbH)

Specific heats of Zr-2.5Nb pressure tube material have been measured by differential scanning calorimetry (DSC) between 100°C and 1200°C using a heating and cooling rate of 20°C/min. A hysteresis was observed in the specific heat curves between heating and cooling. A maximum value occurs at a higher temperature on heating than on cooling, and the magnitude is larger for cooling when compared to heating. The as-manufactured tube material showed a small enthalpy change during first heating, attributed to decomposition of meta-stable β-Zr; and this did not appear on second heating after being first heated to 1200°C. Further studies are suggested to characterize the hysteresis behaviour.

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11:20 - 11:40 - Montagu II

THERMAL EXPANSION ANISOTROPY OF ZR-2.5NB PRESSURE TUBE MATERIAL ON HEATING TO 1100°C

R. W. L. Fong (CNL), F. Fazeli, T. Smith (CanmetMATERIALS)

The anisotropic thermal expansion (and contraction) properties of Zr-2.5Nb pressure tube material have been investigated up to 1100°C using a high-resolution dilatometer. The thermal expansion measured along two principal axes of the pressure tube (longitudinal and transverse directions) are compared with calculated values from a derived expression with material parameters (e.g., single-crystal thermal coefficients (alpha and ß phase), texture, phase volume fractions, and phase transformation strain. The calculated thermal expansion is shown to capture the thermal expansion and anisotropic characteristics throughout the phase transformation regime (two phase region) and into the high-temperature single ß-phase domain.

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2B4 -Safety and Licensing (II)

10:00-12:00 - Montagu IIICo-Chairs: Wei Shen (CNSC);

Mark McIntyre (Atlantic Nuclear Inc)

10:00 - 10:20 SEVERE ACCIDENT ANALYSIS OF A STEAM GENERATOR TUBE RUPTURE ACCIDENT USING MAAP-CANDU TO SUPPORT LEVEL 2 PSA FOR THE POINT LEPREAU STATION REFURBISHMENT PROJECT

S. Petoukhov, M. Brown (CNL)

10:20 - 10:40 QUANTIFYING THE CONTRIBUTION OF ALEATORY AND EPISTEMIC UNCERTAINTIES IN THE ESTIMATION OF PROBABILITY OF FAILURE OF PRIMARY PIPING

M. Jyrkama, M. Pandey (University of Waterloo)

10:40 - 11:00 ESTABLISHMENT OF CHANNEL SPECIFIC CHANNEL AND BUNDLE POWER LIMITS

J. H. Choi, D. J. Park, H. K. Ahn, B. G. Kim, C. J. Choi (KEPCO E&C), D. W. Kho (KHNP-CRI), S. M. Kim (KHNP-CRI)

11:00 - 11:20 EFFECT OF FLOW CONDITIONS ON FLOW ACCELERATED CORROSION IN PIPE BENDS

H. Mazhar (CNL), C. Ching (McMaster University)

11:20 - 11:40 STUDY ON START TIME OF PARAMETRIC STUDY FOR CHANNEL ANALYSIS UNDER SBLOCA/LOECI

B. Moon, E. K. Jang, S. R. Kim (Nuclear Engineering Service & Solution)

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Session: 2B4 -Safety and Licensing (II) Paper Abstracts / Sommaires

10:00 - 10:20 - Montagu III

SEVERE ACCIDENT ANALYSIS OF A STEAM GENERATOR TUBE RUPTURE ACCIDENT USING MAAP-CANDU TO SUPPORT LEVEL 2 PSA FOR THE POINT LEPREAU STATION REFURBISHMENT PROJECT

S. Petoukhov, M. Brown (CNL)

A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. The MAAP-CANDU code was used to simulate the progression of postulated severe core damage accidents and fission product releases.

This paper discusses the analysis results for the reference case of the Steam Generator Tube Rupture accident scenario, one of eight cases simulated for this initiating accident. The reference case assumed most safety-related plant systems were not available: the steam generator feedwater; the emergency water supply; the moderator, shield and shutdown cooling systems; and all stages of the emergency core cooling.

The simulation predicted that severe core damage began at 3.7 h, containment failed at 6.4 h, the moderator boiled off by 8.2 h, and the calandria vessel failed at 42 h. A total release of 5.3% of the initial inventory of radioactive isotopes of Cs, Rb and I was predicted by the end of the simulation (139 h). Almost the entire initial noble gas inventory in the core was transported with the containment atmosphere to the environment, primarily after the containment failure. No hydrogen/carbon monoxide burning was predicted in the containment.

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10:20 - 10:40 - Montagu III

QUANTIFYING THE CONTRIBUTION OF ALEATORY AND EPISTEMIC UNCERTAINTIES IN THE ESTIMATION OF PROBABILITY OF FAILURE OF PRIMARY PIPING

M. Jyrkama, M. Pandey (University of Waterloo)

The impact of aleatory (random) and epistemic (lack of knowledge) uncertainty on the probability of failure is typically quantified through a two-staged nested simulation approach. Addressing the regulatory concern over the confidence of the results has thus far had limited discussion in the literature. This paper shows how the two-staged approach can be used for modeling parameter uncertainty and analyzing sensitivity, which are unrelated to the confidence in the probability of failure. The results demonstrate how the uncertainty in the overall probability of failure depends only on the sampling error from simulation, not the input variable uncertainty or their separation.

10:40 - 11:00 - Montagu III

ESTABLISHMENT OF CHANNEL SPECIFIC CHANNEL AND BUNDLE POWER LIMITS

J. H. Choi, D. J. Park, H. K. Ahn, B. G. Kim, C. J. Choi (KEPCO E&C), D. W. Kho (KHNP-CRI), S. M. Kim (KHNP-CRI)

A study on the establishment of channel-specific channel and bundle power limits for a CANDU 6 plant in Rep. of Korea was done. Rationale for the establishment of channel-specificchannel and bundle power limits and the selection of single channels for detailed safety evaluation, and the results of LOCA analysis with established channel and bundle power limits are included in this paper. A safety evaluation, with final limits for channel-specific channel and bundle powers, shows that the times to reach acceptance criteria are very close to each other for nine selected single channels in accordance with the basic principles for the establishment of channel and bundle power limits.

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11:00 - 11:20 - Montagu III

EFFECT OF FLOW CONDITIONS ON FLOW ACCELERATED CORROSION IN PIPE BENDS

H. Mazhar (CNL), C. Ching (McMaster University)

Flow Accelerated Corrosion (FAC) in piping systems is a safety and reliability problem in the nuclear industry. In this study, the pipe wall thinning rates and development of surface roughness in pipe bends are compared for single phase and two phase annular flow conditions. The FAC rates were measured using the dissolution of test sections cast from gypsum in water with a Schmidt number of 1280. The change in location and levels of maximum FAC under single phase and two phase flow conditions are examined. The comparison of the relative roughness indicates a higher effect for the surface roughness in single phase flow than in two phase flow.

11:20 - 11:40 - Montagu III

STUDY ON START TIME OF PARAMETRIC STUDY FOR CHANNEL ANALYSIS UNDER SBLOCA/LOECI

B. Moon, E. K. Jang, S. R. Kim (Nuclear Engineering Service & Solution)

The channel behavior under SBLOCA with LOECI is analyzed. A small break is postulated to occur in the PHTS and the coolant discharges continuously without makeup. Eventually the inventory in the broken loop depleted and the loop begins to be filled with steam. For the analysis of channel behavior under this condition, the parametric study based on steam flow is conducted for the consideration of limiting condition. The channel does not fail as decay heat is transferred to moderator through ballooning or sagging contact. In this analysis, the effect of start time of parametric study on the contact behavior is estimated for 2.5% RIH break for Wolsong-2 NPP using CATHENA 3.5.4.4.

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Conference Luncheon & CNS/CNA Honours and Awards Ceremony

12:00-14:00 - Marco Polo

Plenary 2A: Enterprise Risk Management14:00-15:30 - Loyalist

Chair: Joy Shikaze (Women in Nuclear)

14:00 ENTERPRISE RISK MANAGEMENT C. Eaton (Enbridge)

14:15 MANAGING RISK FOR A NUCLEAR GENERATOR

C. Cosby (Bruce Power)

14:30 THE IMPORTANCE OF LEADERSHIP G. T. Thomas (President & CEO, New Brunswick

Power)

14:45 TECHNICAL CONSCIENCE P. Freeman (INPO)

15:00 RISK CONTROL AND NUCLEAR LIABILITY C. DeMerchant (NIAC)

Women in Nuclear (WiN) Canada’s Executive Director, Joy Shikaze, is an award-winning accredited public relations professional with hands-on experience as a senior project manager, facilitator, media relations expert and crisis communications specialist. Through managing her own consulting business, Joy has extensive experience in media relations, government relations and communications strategy for business, associations and not-for-profit organizations. One of Joy’s specialties is her unique talent to coach everyone in an organization from the frontline customer service workers to the C-Suite executives to be confident communicators. Her true success shows in empowering leaders to manage their message.


JOY SHIKAZE

WOMEN IN NUCLEAR

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Chris Eaton is director of enterprise Risk management for Enbridge Inc. He is also in the final stage of completing a PhD in risk management through the University of Calgary’s Haskayne School of Business. Prior to commencing his doctoral studies, Chris worked in industry and consulting for about 15 years with a focus on risk management in the energy/utility industry. Two of his recent roles included director of risk management for ENMAX and a senior manager in Deloitte’s Enterprise Risk Services practice.

Chris is fascinated by the innovation of risk governance and the articulation of acceptable risk—topics addressed through his doctoral research. He has authored and co-authored a number of risk-related papers and reports, presented at leading practitioner and academic conferences, and contributed to professional organizations. He has also developed and delivered risk-related educational courses and professional training for a wide range of groups, from undergraduate students to corporate directors.

Chris holds a BBA (honours) from Simon Fraser University and an MBA from Queen’s University. He lives in Calgary with his wife, Tania, and two daughters, Claire (6 years old) and Elizabeth (4 years old).


CHRISTOPHER EATON P.Eng

ENBRIDGE INC.

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Experience:

• 2014 – Present: Institute of Nuclear Power Operations; Sr. Team leader corporate evaluations; Atlanta GA

• 2012-2013: NextEra Energy: Corporate Vice President of Organizational Effectiveness – Juno Beach FL; Responsible for fleet Regulatory Compliance, Training, Performance Improvement and Corrective Action, Security

• 2009- 2012: NextEra Energy: Site Vice President – Seabrook Station; Seabrook NH

• 2008- 2009: NextEra Energy: Plant General Manager – Seabrook Station; Seabrook NH

• 2003- 2008: NextEra Energy: Engineering Director – Seabrook Station; Seabrook NH

Education:

• Boston College: Master of Business Administration

• Massachusetts Maritime Academy: Bachelor of Science in Marine Engineering

Licenses:

• US Nuclear Regulatory Commission Reactor and Senior Reactor Operator license 1989 - 2001


PAUL FREEMAN

INSTITUTE OF NUCLEAR POWER OPERATIONS

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General Manager Colleen P. DeMerchant FCIP, CRM Colleen DeMerchant has been involved with NIAC for almost 20 years and is recognized internationally and domestically as subject matter and insurance risk expert in the complex and closely regulated area of Canadian nuclear insurance. Colleen has appeared before the Standing Committee on Natural Resources regarding changes to the Nuclear Liability Act and has participated in international conferences on civil liability for nuclear damage and nuclear symposiums to spread the word of Canada’s unique domestic pooling arrangements. Colleen began her insurance career with a regional brokerage in Saint John, New Brunswick. Following several years as broker, she moved to Toronto to take up a Head Office underwriting position for one of Canada’s leading Property/Casualty insurers for more than ten years before joining the Insurers’ Advisory Organization (IAO) as Casualty Manager prior to NIAC. Promoted to General Manager in 2012, Colleen directs NIAC’s strategic plan, in accordance with the Governing Committee and provides leadership to insurance and nuclear industries and federal government on nuclear liability risk, insurance, loss control and claims administration. Colleen also is responsible for preparing and reviewing NIAC’s financial activities and member solicitation requirements set by the Office of the Superintendent of Financial Institutions (OSFI). Colleen has authored papers on nuclear liability insurance in Canada as well as explaining the nuclear insurance exclusion in the IBC industry standard general liability wording and she has conducted continuing education seminars for the insurance community.


COLLEEN P. DEMERCHANT NUCLEAR INSURANCE ASSOCIATION OF CANADA

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Plenary 2B: Vendor Role in a Continuously Improving Industry - Panel Discussion

16:00-17:30 - LoyalistChair: Ron Oberth

(Organization of Canadian Nuclear Industries)

PANEL MEMBERS Shawn Sarkar, (Sartrex)

Keith Scott, (WorleyParsons) Vince Robinson, (Tyne Engineering) Brian Thorne, (NB Power) Scott Malcolm, (SNC-Lavalin)

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Dr. Ron Oberth has worked in the Canadian nuclear industry for more than 30 years at Ontario Hydro, Ontario Hydro International, Ontario Power Generation and AECL Reactor Division (now Candu Energy). In June of 2011 Ron became president of the Organization of Canadian Nuclear Industries (OCI) - an industry association that represents 180 private sector companies that supply equipment and services to CANDU and other nuclear power plants in Canada and offshore. His nuclear experience includes reactor safety, used fuel management, medical isotopes, and the marketing of CANDU reactors both domestically and internationally. Ron is a graduate of the University of Manitoba and the Rotman School of Business and received his PhD from Princeton University.


DR. RON OBERTH

ORGANIZATION OF CANADIAN NUCLEAR INDUSTRIES

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Shawn Sarkar holds a BSc (Hons) degree as well as an MBA from the Schulich School of Business where he specialized in International Business and Strategic Management. As Executive Vice President/QA Director of Sartrex Power Control Systems Inc., design and manufacturer of nuclear control & safety instrumentation, his main focus is to leverage his Company’s 37 years of expertise into innovative design and manufacturing solutions, for quality driven industries. His position has directly exposed him to the evolving requirements of the nuclear utility’s commercial, technical and quality departments. This provides him a unique perspective on the everyday challenges a supplier faces, but more importantly, the exposure has allowed him to identify ways that suppliers can add more value to their own businesses, while at the same time enhance the success and growth of this industry.


SHAWN SARKAR

SARTREX POWER CONTROL SYSTEMS INC.

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Vince Robinson is President of Tyne Engineering. Tyne Engineering is a supplier of Commercial Grade Dedication, and is a designer and builder of custom electronics and skid-mounted process systems for the nuclear industry both in Canada and abroad. Mr. Robinson has worked at Tyne Engineering for over 15 years, and has spent time in sales, project management, R&D, and quality assurance. Through these departments, Vince has gained a good understanding of the challenges and needs of both customer and supplier in the interesting and challenging nuclear industry.


VINCE ROBINSON

PRESIDENT, TYNE ENGINEERING

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Scott Malcolm is Vice-President, CANDU Services and as such is responsible for business development and sales for the Services business line. He has 28 years of experience in design and commercial operations of high technology companies, including over 20 years at Atomic Energy of Canada Ltd. (AECL).Scott spent 18 years in nuclear design at AECL and five years outside the nuclear industry in naval surface ship design. More recently he spent the last four years in senior commercial roles at AECL in the after sales services organization where as General Manager, he was responsible for managing a $130 million a year business, including product development, proposals and customer relations.Scott transitioned to Candu Energy, member of the SNC-Lavalin group, in 2011. Before that he held positions of Manager, Instrumentation, Control and Electrical Engineering, Section Head, Control Centre and Human Factors Design, and Principal Design specialist in Human Factors at AECL. He was responsible for a wide range of engineering services, including control centre modifications to existing plants and support to advanced control centre designs such as the Advanced CANDU Reactor. Scott was a key developer of the process for incorporating human factors engineering into the Canadian nuclear industry, including a strong focus on the development of control centre functionality and supporting technology.Scott has over 15 years of experience developing nuclear design standards and is a former Chair of the Institute of Electrical and Electronic Engineers (IEEE) Nuclear Power Engineering Committee and the Chief Canadian Delegate to the International Electrotechnical Commission (IEC) in the area of nuclear instrumentation. He has a Masters degree in Human Factors/Ergonomics from the University of Guelph in Ontario, Canada (1985) and is a Certified Human Factors Specialist (CHFP) from the Board of Certification in Professional Ergonomics (U.S.).


SCOTT MALCOLM

VICE-PRESIDENT, CANDU SERVICES

108


Conference Cocktail Reception with music by

Saint John String Quartet 18:30-19:30, Montagu I-III and Foyer.

Conference Banquet and Entertainment by

Vinyl2Bits SHOWBAND19:30-23:00, Marco Polo

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110

WEDNESDAY JUNE 3 / MERCREDI 3 JUIN

Breakfast for Speakers & Chairs of the Day07:00-07:45 - Montagu I & II


Plenary 3A: Waste Management and Decommissioning08:00-09:45 - Loyalist

Chair: David Legault (WorleyParsons)

08:00 IMPLEMENTING CANADA’S PLAN FOR THE LONG-TERM MANAGEMENT OF USED NUCLEAR FUEL

D. Wilson (NWMO)

08:15 SHUTDOWN OF PICKERING STATION L. Swami (OPG)

08:30 MANAGING OUR NUCLEAR LEGACY LIABILITIES

J. Miller (CNL)

08:45 REGULATORY OVERSIGHT OF NUCLEAR WASTE AND DECOMMISSIONING

R. Jammal (CNSC)

09:00 INTERNATIONAL OVERVIEW ON STATUS AND FUTURE DEVELOPMENTS IN DECOMMISSIONING OF NPP

M. Siemann (NEA/OECD)


111


Dave is the Vice President of ‘Restoration’ at WorleyParsons. He is responsible for the delivery of legacy liability management services to Power Sector customers in North America.Dave is a professional Geoscientist registered in Ontario, and is a graduate of the University of Waterloo where he combined Earth Sciences and Management studies. He began his career as an exploration geologist, prospecting for diamonds across Canada and the outback of Australia. His career focus shifted in the late 80’s, to the emerging environmental industry. Since then, he has helped hundreds of customers across a broad range of industry sectors manage their environmental risks and liabilities. Within the nuclear sector, Dave has imported expertise from United Kingdom and the United States in the delivery of projects in Canada. Dave is currently a member of the Innovation Canada Alliance (ICA) team in hot pursuit of the restructuring of Canadian Nuclear Laboratories.In his personal time, Dave likes to travel ‘developing countries’, and has back-packed in all continents, with the sole exception of Antarctic – so far!His passion is in land stewardship, and he is actively engaged in the preservation of ecology habitats, for the benefit of wildlife.


DAVID LEGAULT

WORLEYPARSONS

112


Derek is the Vice President of Design and Construction at the NWMO. He is responsible for the implementation of the APM technical program, as well as, the NWMO Project Manager for the Ontario Power Generation Low and Intermediate Level Waste Deep Geologic Repository project. Derek is a mining engineer with over 20 years experience in the mining and heavy construction industries, primarily in project and operational management roles. Prior to joining the NWMO, he was a Project Manager with the Mining division of AMEC responsible for the development of the resource projects in Canada, after spending a decade with Holcim Canada.


DEREK WILSON

NUCLEAR WASTE MANAGEMENT ORGANIZATION

113


As Senior Vice President Decommissioning and Nuclear Waste Management Ms Swami’s responsibilities include establishing the scope of work necessary to prepare for Pickering End of Commercial Operations, implement strategic waste management projects (such as the OPG’s Low and Intermediate Level Nuclear Waste Deep Geologic Repository and Ontario’s Nuclear Power Reactor Decommissioning) and oversee the day to day operations of OPG’s waste management facilities. In addition, she holds the portfolio for OPG’s Nuclear Regulatory Affairs.

Ms Swami joined Ontario Hydro (Ontario Power Generation) in 1986 and has since held a variety of Engineering and Managerial positions, including Radiation Protection Manager (Pickering B), Chemistry Manager (Pickering A and B), and Director Environment (All Nuclear), Director of EA and Licensing (Darlington New Nuclear Project), Vice President of Nuclear Regulatory Programs and Vice President of Nuclear Services.

Ms Swami graduated from Queen’s University in 1985 with a Bachelor of Science degree in Engineering Chemistry. In 1994, she received a Masters of Business Administration from York University.

She lives with her family in Pickering, Ontario.


LAURIE SWAMI


114


Joan Miller is Vice-President of Decommissioning & Waste Management for Canadian Nuclear Laboratories Limited (CNL).*

CNL’s Decommissioning & Waste Management unit has responsibility for the delivery of the Government of Canada programs for nuclear legacy liabilities and low-level radioactive historic wastes, management of operational wastes at CNL’s Chalk River Laboratories site, and development of the technical capabilities for decommissioning, waste management and environmental remediation activities required to support Canada’s nuclear science and technology programs now and in the future.

Joan has spent her 35 year career in the nuclear industry with AECL. Over the years, she has gained extensive experience in research & development programming, product & services development, facility operations and engineering projects, at the operations, planning and management level. Joan has been responsible for the decommissioning and waste management portfolio since 2007.


JOAN MILLER

SENIOR VICE PRESIDENT, DECOMMISSIONING AND NUCLEAR WASTE MANAGEMENT CANADIAN NUCLEAR LABORATORIES

115


Ramzi Jammal has worked for the CNSC since 1998, holding progressively senior positions. He has accumulated over 30 years of experience in the nuclear industry, combining management skills with scientific expertise, and representing the CNSC in various international activities. These include the development and establishment of the IAEA Code of Conduct for the Safety and Security of Radioactive Sources, and the international categorization of radioactive sources. He also played a key role in ensuring that the recommendations of the International Commission on Radiation Protection complemented the CNSC’s regulatory needs and currently co-chairs the IAEA Working Group on Fukushima Comprehensive Report. He holds a Bachelor of Science in Engineering Physics, a Masters in Medical Physics and a Masters of Business administration


RAMZI JAMMAL MBA, MSc, BSc

EXECUTIVE VICE-PRESIDENT AND CHIEF REGULATORY OPERATIONS OFFICERREGULATORY OPERATIONS BRANCH, CANADIAN NUCLEAR SAFETY COMMISSION

116


Michael Siemann has been with the OECD Nuclear Energy Agency in Paris, France, since July 2012. As Head of the Division of Radiological Protection and Radioactive Waste Management, he is member of the executive leadership family of the NEA and responsible for radioactive waste management, decommissioning of nuclear facilities, emergency preparedness and management, radiation protection and public health. His positions before joining the OCED NEA, in reverse chronological order, were at:• Federal Office for Radiation Protection (BfS) in Germany, as Head of

Department, Safety of Nuclear Waste Management Department, with responsibility for implementation and operation of all German repository projects for radioactive waste and licensor for all transports and storage of nuclear fuel

• Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) in Germany, as Senior Government Official with supervisory control of the final repository for LILW Assessment

• Technical University Clausthal in Germany as Senior Scientist and Assistant Professor at the Institute for Repository Research, Department for Geochemistry Salt deposits and Underground Repositories, and Head of the research group “Evaporites” and of analytical and experimental laboratories

• Federal Office for Radiation Protection (BfS) as Science officer for Planning, Coordination and Management of site specific research and development for “Gorleben” as a potential site for a HAW repository, and for Coordination of Research and Development for Radioactive Waste Management with other Organisations and Ministries in Germany.


DR. MICHAEL SIEMANN

OECD NUCLEAR ENERGY AGENCY

117


Plenary 3B: Developing Technologies and Resources10:15-12:00 - Loyalist

Chair: Robert Walker, CNL

10:15 R&D AT THE UNIVERSITIES B. Shalaby (UNENE)

10:30 DEVELOPING TECHNOLOGIES AND RESOURCES

R. Walker (CNL)

10:45 PROFESSIONAL DEVELOPMENT AND EXTENSION PROGRAMS

G. Bereznai (UOIT)

11:00 THE IMPORTANCE OF INDUSTRIAL R&D AND COLLABORATION

R. Whalen (SNC-Lavalin)

11:15 NUCLEAR INNOVATION IN SASKATCHEWAN

N. Alexander (Sylvia Fedoruk Canadian Centre for Nuclear Innovation, U Saskatchewan)

118


Dr. Robert Walker was appointed President and Chief Executive Officer of Canadian Nuclear Laboratories Limited (CNL) effective November 3, 2014. CNL is a wholly-owned subsidiary of Atomic Energy of Canada Limited (AECL).

Concurrent to his position at CNL, Dr. Walker also served as AECL’s President and Chief Executive Officer from October 7, 2011 to March 31, 2015. Dr. Walker joined AECL in November 2010 as the Senior Vice-President of AECL’s Nuclear Laboratories division.

Dr. Walker has had a distinguished career in the Government of Canada, with more than 25 years of leadership experience in science and technology management and 10 years experience in conducting defence research and exploratory development, both at progressively senior levels.

Prior to joining AECL, Dr. Walker was the Assistant Deputy Minister of Science and Technology at the Department of National Defence and the Chief Executive Officer of Defence Research and Development Canada. He was also the Federal Government’s executive responsible for coordinating its public safety science and technology activities.

For the period April 2009 to 2012, Dr. Walker served as the Chairman of the NATO Research and Technology Board, the senior oversight body for cooperative research within the NATO framework. He is presently the Chair of the Board for the Network of Centres of Excellence in Marine Environmental Observation, Prediction and Response (MEOPAR), hosted by Dalhousie University. Dr. Walker also serves as the Governance Chair of the Canadian Nuclear Association Board of Directors and as member of the Executive Committee.

Dr. Walker earned a B.Sc. in Physics from Acadia University, an M. Eng. in Engineering Physics and a Ph.D. in Electrical Engineering from McMaster University. In 2013, McMaster University awarded Dr. Walker with an honorary Doctor of Science degree. He is a graduate of the National Defence College and a Fellow of the Canadian Academy of Engineering. Dr. Walker is the recipient of the Canadian Forces Medallion for Distinguished Service.


DR. ROBERT S. WALKER FCAE

PRESIDENT AND CEO OF CNL

119


Basma A. Shalaby is a senior Design Engineer with 34 years experience with former AECL Engineering division. Following her retirement in 2009 she accepted her currently position as the President of UNENE (aka University Network for Excellence in Nuclear Engineering).

Prior to retirement Basma was AECL`s Chief Engineer for 11 years. Basma started her career as a process and safety system design engineer at AECL, and then held many technical senior positions in CANDU design and development, within AECL and CANDU Owners Group (COG).

She has a B. Sc. (University of Cairo), an M.A. Sc. in Chemical Engineering (University of Waterloo) and an Honorary Doctorate Degree in Engineering from the University of Waterloo (2005).

Basma received many professional awards; Global Wisdom Award (2004) from “Key Women in Energy”, the G.L. Brooks Engineering Award from AECL for exceptional practical engineering in 2005.

During her 34 year career she represented Canada in many International Nuclear Advisory Groups and HWR Working Groups at the IAEA.

She has numerous technical publications on CANDU technology design, and related topics.


DR. BASMA A. SHALABYUNIVERSITY NETWORK OF EXCELLENCE IN NUCLEAR ENGINEERING

120


Dr. George Bereznai is a professor and director of industry training programs at the Faculty of Energy Systems and Nuclear Science at the University of Ontario Institute of Technology (UOIT), Oshawa, Ontario, Canada.

Prior to joining UOIT, Dr. Bereznai worked for 30 years in Ontario Hydro’s nuclear division where he was responsible for full scope training simulators and the use of computers in training. Part of these years was spent internationally, including six years in Bangkok, Thailand as the Atomic Energy of Canada Limited chair in Nuclear Engineering at Chulalongkorn University.

Dr. Bereznai is a professional engineer, having obtained a Bachelor of Engineering degree from the University of Adelaide in Australia, a Master of Engineering in Electrical Engineering and Ph.D. in Electrical Engineering from McMaster University in Hamilton, Ontario. His research interests are computer control of nuclear power plants, real-time simulation and educational technology.


DR. GEORGE BEREZNAI

UNIVERSITY OF ONTARIO INSTITUTE OF TECHNOLOGY

121


Rob Whalen is responsible for all engineering activities in SNC-Lavalin’s Nuclear business unit. In this capacity, he leads a team of over 800 nuclear steam plant and balance of plant engineers dedicated to the highest standards in the industry. Rob oversees all engineering activities including tooling and refurbishment tooling engineering as well as the development of CANDU® reactors.

Before joining SNC-Lavalin in 2015, Rob was most recently Vice President, Nuclear Engineering for Tennessee Valley Authority (TVA) in the United States. While there, he transformed the Nuclear power group engineering from a reference source model to a highly valued technical team, while leading significant improvement in equipment reliability and resolution of significant historical regulatory issues. Rob was instrumental in building a strong technical conscience in the Engineering organization at TVA and in developing a strong and diverse leadership team focussed on collaborative leadership and industry best practices.

Rob brings a true operator’s viewpoint to SNC-Lavalin, with more than 30 years of commercial nuclear power plant experience. He has worked at four nuclear stations and also spent two years on assignment with INPO as a senior evaluator, supporting nuclear plant evaluations and assistance. His site experience includes responsibilities for site engineering, site maintenance and maintenance planning.

He holds a Bachelor of Science in Mechanical Engineering from Purdue University and a American National Standards Institute (ANSI) Senior Reactor Operator (SRO) certification from a US boiling water reactor site. Rob completed the Institute of Nuclear Power Operations (INPO) Senior Nuclear Plant Manager’s Program in 2007. Rob has been a member of the advisory boards of the University of Tennessee Knoxville and Auburn University in Alabama. He previously served in executive leadership roles on the US Boiling Water Reactor Owners Group and the Pressurized Water Owner’s Group, and served on the Electric Power Research Institute (EPRI) Nuclear Power Council.


ROBERT WHALENSNC-LAVALIN

122


Dr. Neil Alexander has been the Executive Director of the Fedoruk Centre since July 2014. Prior to that, he served in a number of senior executive roles in the Canadian nuclear industry, including: President and General Manager of Rolls-Royce Civil Nuclear Canada, President of the Organization of CANDU Industries, and as Vice-President of Business Development with SNC-Lavalin Nuclear.

With a Ph.D. in metallurgy from the University of Birmingham (UK), Dr. Alexander has a broad experience of the nuclear industry that includes nuclear power, radioisotope production and management of radioactive wastes. He has been a long-term and active promoter of the benefits of nuclear power as a sustainable approach to managing some of the world’s most significant environmental challenges.


DR. NEIL ALEXANDERSYLVIA FEDORUK CANADIAN CENTRE FOR NUCLEAR INNOVATION

123



DR. JOHN W. HILBORNAECL, RETIRED

Conference Luncheon & Guest Speaker12:00-14:00 - Marco Polo

13:00 - 14:00 70TH ANNIVERSARY OF ZEEP AND CONTROLLED FISSION IN CANADA

J. Hilborn (AECL Retired)

Dr. John Wells Hilborn began his career in the nuclear industry in 1949 at the Port Radium Eldorado uranium mine in the Northwest Territories. He received a Ph.D. in nuclear physics in 1954 from McGill University in Montréal, Québec. He joined Atomic Energy of Canada Limited in 1954 as a researcher and contributed to the design and start-ups of the Nuclear Research Universal (NRU) reactor (NRU) at Chalk River, the Nuclear Power Demonstration (NPD) reactor at Rolphton, Ontario, and the Whiteshell Reactor -1 (WR-1) at AECL’s Whiteshell Nuclear Research Establishment, Whiteshell, Manitoba. In addition, he participated in the Steam Generator Heavy Water reactor (SGHW) experiment at Harwell, U.K.

In 1964, he demonstrated the feasibility of the self-powered neutron detector, used today for nuclear-reactor in-core monitoring at nuclear stations around the world. This detector was patented in 1967 and manufactured by the nuclear instrumentation company Reuter-Stokes Canada Ltd. From 1972 to 1977, Dr. Hilborn headed a new branch at Chalk River to develop special methods and tools for the non-destructive inspection of CANDU-reactor pressure tubes and steam generators. In 1974, Dr. Hilborn was awarded the Thomas W. Eadie Medal by the Royal Society of Canada and the prestigious W.B. Lewis Medal by the Canadian Nuclear Association. In 2013, he was awarded the Queen’s Diamond Jubilee Medal, and in 2014, he was awarded the W.E. Havercroft Medal by the Canadian Institute for Non-Destructive Examination.

Dr. Hilborn made another very important contribution by developing the SLOWPOKE nuclear reactor concept (the acronym stands for Safe LOW POwer Critical (K) Experiment), a pool-type nuclear reactor for research. The SLOWPOKE allowed several universities to acquire and operate nuclear research facilities at an affordable cost, and to develop high-level nuclear-science and engineering programs and high-quality personnel dearly for the Canadian nuclear industry.

124


3A1 - Panel Discussion on Transportation of Used Nuclear Fuel

14:00-15:20 - LoyalistChair: Elena Mantagaris

(Nuclear Waste Management Organization)

14:00 - 14:20 TRANSPORT OF NUCLEAR USED FUEL AND WASTE MATERIALS

H. J. NEAU (WNTI)

14:20 - 14:40 UK TRANSPORT OF IRRADIATED FUEL R. James (EDF Energy (UK))

14:40 - 15:00 TRANSPORT OF NUCLEAR SUBSTANCES IN CANADA

S. Faille (Canadian Nuclear Safety Commission)

15:00 - 15:20 SAFE AND SECURE: TRANSPORTATION OF RADIOACTIVE MATERIALS

D. Howe (Ontario Power Generation)

15:20 - 15:40 OVERVIEW OF NWMO’S TECHNICAL TRANSPORTATION PROGRAM


15:40 - 16:00 OVERVIEW OF NWMO TRANSPORTATION ENGAGEMENT PLAN

J. A. Facella (Nuclear Waste Management Organization)

125


3A2 – Refurbishment and Life Extension (II)14:00-15:20 - Montagu I

Co-Chairs: Bruce Gorham (Atlantic Nuclear Inc.) ; Matthew Daley (CNL)

14:00 - 14:20 APPLICABILITY OF ANSYS ELBOW290 ELEMENT FOR FLEXIBILITY CALCULATION OF TIGHT RADIUS BENDS ON FEEDER PIPES IN CANDU REACTORS

X. Zhang (Candu Energy Inc.)

14:20 - 14:40 COMPARATIVE STATIC SIMULATIONS OF A CANDU6 CELL USING DIFFERENT TRANSPORT CODES

M. MAHJOUB, Jean Koclas (École Polytechnique de Montréal)

14:40 - 15:00 PRELIMINARY DEVELOPMENT AND MODELING OF A NEXT GENERATION INSPECTION SYSTEM FOR CANDU PRESSURE TUBES

J. Gilbert, M. Manning, S. Nokleby, E. Waller (UOIT)

15:00 - 15:20 INNOVATIVE PIPE THICKNESS VERIFICATION FOR FEEDWATER FLOW AT DARLINGTON NUCLEAR POWER GENERATING STATION

V. Ton, J. Kim, C. Zhao (Ontario Power Generation)

126


Session: 3A2 – Refurbishment and Life Extension (II)Paper Abstracts / Sommaires

14:00 - 14:20 - Montagu I

APPLICABILITY OF ANSYS ELBOW290 ELEMENT FOR FLEXIBILITY CALCULATION OF TIGHT RADIUS BENDS ON FEEDER PIPES IN CANDU REACTORS

X. Zhang (Candu Energy Inc.)

A curved pipe element, ELBOW290, became available in ANSYS®12. This element was developed based on a simplified shell theory, and maintains the ability to capture cross-sectional deformations of elbows. Numerical testing on the applicability of this element for the flexibility calculation of the tight radius bends in CANDU® reactors is carried out to determine the usability of this element in completing stress analyses for feeder pipes. Comparisons are made between the ELBOW290 and the shell element for various feeder bend types found in domestic and overseas CANDU reactors. The comparisons show that the ELBOW290 element is suitable for calculating the flexibility of the tight radius bends.

127


14:20 - 14:40 - Montagu I

COMPARATIVE STATIC SIMULATIONS OF A CANDU6 CELL USING DIFFERENT TRANSPORT CODES

M. MAHJOUB, M. M. Jean Koclas (École Polytechnique de Montréal)

The solution of the time dependent Boltzmann equation remains quite a challenge. We are in the process of developing such a method using the stochastic Monte Carlo approach for two reasons: First, at the cell level, we will be able to obtain time dependent homogenized cross sections for use in full core diffusion calculations. Second, the Monte Carlo methods are scalable to perform full core if and when appropriate computer resources become available.

The Time dependent approach will be concretized a new module that will be added to an existing Monte Carlo code. As a first step towards this goal, we need to choose the initial Monte Carlo code to be used as start point. For this reason, we have compared results concerning the void reactivity of a fresh fuel CANDU6 cell, using two Monte Carlo codes, namely VTT developed SERPENT and MIT developed OpenMC together with the deterministic DRAGON code. Several libraries are used in this comparison. We conclude that OpenMC is a good candidate for implementation of a time dependent simulation.

14:40 - 15:00 - Montagu I

PRELIMINARY DEVELOPMENT AND MODELING OF A NEXT GENERATION INSPECTION SYSTEM FOR CANDU PRESSURE TUBES

J. Gilbert, M. Manning, S. Nokleby, E. Waller (UOIT)

This paper will look at the development of a next generation inspection system for CANDU pressure tubes. The inspection system will be an autonomous crawler and will incorporate a full pressure closure plug which will not require the use of the current Universal Delivery Machine (UDM). By not requiring the UDM this new inspection package will allow for the potential of multiple inspections simultaneously, as well as freeing up the fueling machine bridge for other work. In conjunction with this new inspection system, an MCNP [1] simulation of the offline core conditions is being developed. This simulation will allow for estimates to be made of the dose that the inspection system will encounter, thereby allowing for more accurate prediction of component lifetimes.

128


15:00 - 15:20 - Montagu I

INNOVATIVE PIPE THICKNESS VERIFICATION FOR FEEDWATER FLOW AT DARLINGTON NUCLEAR POWER GENERATING STATION

V. Ton, J. Kim, C. Zhao (Ontario Power Generation)

Darlington nuclear generating station (DNGS) uses externally mounted Ultrasonic Flow Meter (UFM) to verify its feedwater flow rate for the heat balance program. Recently a WANO operating experience (OPEX – WER ATL 14-0448) has identified an issue with the pipe thinning under the externally mounted UFM transducer area in PWR plants, consequently the flow correction factor had been slowly trending in the non-conservative direction. Therefore, DNGS needs to assess the implication of this OPEX and confirm if the pipe thinning is occurring beneath DNGS’s UFM brackets. This report is to summarize the action taken on the piping thickness measurements and the results in a cost effective way. Additional, the results are also verified with FAC (flow accelerated corrosion) monitoring data.

129


3A3 - Safety and Licensing (III) 14:00-15:40 - Montagu II

Co-Chairs: Mikko Jyrkama (University of Waterloo); Jacques Plourde (Nuclear Insurance Association of Canada)

14:00 - 15:20 CONSERVATISM IN METHDOLOGIES FOR MODERATOR SUBCOOLING SUFFICIENCY FOR FUEL CHANNEL INTEGRITY UPON PRESSURE TUBE CALANDRIA TUBE CONTACT

L. Sun (Point Lepreau Generating Station, NB Power)

14:20 - 14:40 PLANT HABITABILITY ASSESSMENT FOR POINT LEPREAU GENERATING STATION DURING A SEVERE ACCIDENT RESULTING FROM STATION BLACKOUT CONDITIONS


14:40 - 15:00 WIND HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), M. Moland (New Brunswick Power), J. Sciaudone, L. Twisdale (Applied Research Associates Inc), P. Vickery, D. Mizzen (Applied Research Associates Inc.)

130


Session: 3A3 - Safety and Licensing (III) Paper Abstracts / Sommaires

14:00 - 14:20 - Montagu II

CONSERVATISM IN METHDOLOGIES FOR MODERATOR SUBCOOLING SUFFICIENCY FOR FUEL CHANNEL INTEGRITY UPON PRESSURE TUBE CALANDRIA TUBE CONTACT

L. Sun (Point Lepreau Generating Station, NB Power)

During a postulated large LOCA event in CANDU reactors, the pressure tube may balloon to contact with its surrounding calandria tube to transfer heat to the moderator. To confirm the integrity of the fuel channel in this case, many experiments have been performed in the last three decades. Based on the extant database of the pressure tube/calandria tube (PT/CT) contact, an analytical methodology was developed by Canadian Nuclear Industry to determine the sufficiency of moderator subcooling for fuel channel integrity. At the same time a semi-empirical methodology with an idea of Equivalent Moderator Subcooling (EMS) was also developed to judge the sufficiency of the moderator. In this work, some discussions were made over the two methodologies on their conservatism and it is demonstrated that the analytical approach is over conservative comparing with the EMS methodology. By using the EMS methodology, it is demonstrated that applying glass-peened calandria tubes, the requirement to moderator subcooling can be reduced by 10ºC from that for smooth calandria tubes.

131


14:20 - 14:40 - Montagu II

PLANT HABITABILITY ASSESSMENT FOR POINT LEPREAU GENERATING STATION DURING A SEVERE ACCIDENT RESULTING FROM STATION BLACKOUT CONDITIONS


In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations.

14:40 - 15:00 - Montagu II

WIND HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), M. Moland (NB Power, Point Lepreau Generating Station), J. Sciaudone, L. Twisdale (Applied Research Associates Inc), P. Vickery, D. Mizzen (Applied Research Associates Inc.)

In response to the CNSC Fukushima Action Plan, NB Power has embarked on a wind hazard assessment for the Point Lepreau Generating Station site that incorporates the latest up to date wind information and modeling. The objective was to provide characterization of the wind hazard from all potential sources and estimate wind-driven missile fragilities and wind pressure fragilities for various structures, systems and components that would provide input to a possible high wind Probabilistic Safety Assessment. The paper will discuss the overall methodology used to assess hazards related to tornadoes, hurricanes and straight-line winds, and site walk-down and hazard/fragility results.

132


3A4 - Advanced Fuel Cycles 14:00-15:40 - Montagu III

Co-Chairs: Michael McDonald (CNL); Adriaan Buijs (McMaster University)

14:00 - 15:20 CONTINUING DEVELOPMENT OF A FUEL PERFORMANCE MODEL FOR TH-BASED CERAMIC FUEL

J. S. Bell, P. K. Chan (Royal Military College of Canada)

14:20 - 14:40 A STUDY ON THE OPTIMAL COOLING TIME OF ACTINIDE FEEDSTOCK FOR USE IN TRANSURANIC MIXED OXIDE FUELS IN CANDU REACTORS

A. C. Morreale (CNL), J. C. Luxat (McMaster University)

14:40 - 15:00 PRODUCTIVE ELIMINATION OF NUCLEAR WASTE (PENW): A COMPLEMENTARY BOON FOR CANDUS AND THE CANADIAN NUCLEAR INDUSTRY

P. Ottensmeyer (University of Toronto)

15:00 - 15:20 NATURAL URANIUM EQUIVALENT FUEL - AN INNOVATIVE DESIGN FOR PROVEN CANDU TECHNOLOGY

F. Pineiro, K. Ho, A. Khaial, M. Boubcher, C. Cottrell, S. Kuran (Candu Energy Inc.), Z. Zhenhua, M. Zhiliang (Third Qinshan Nuclear Power Company)


133


Session: 3A4 - Advanced Fuel Cycles Paper Abstracts / Sommaires

14:00 - 14:20 - Montagu III

CONTINUING DEVELOPMENT OF A FUEL PERFORMANCE MODEL FOR TH-BASED CERAMIC FUEL

J. S. Bell, P. K. Chan (Royal Military College of Canada)

A finite element analysis based fuel performance model for Th-based ceramic fuel is being developed. The development of a (Th,Pu)O2 model is novel, and will be capable of providing estimates of fission gas release and sheath/clad strains. Once this model is complete, it will be used to perform a design analysis for the conceptual fuel for the Canadian SCWR pellets and cladding. Results obtained for (Th,U)O2 compared with Post Irradiation Examination (PIE) data from the DME-221 irradiation test are encouraging. The current state of the model, as well as modelling results compared to data from a (Th,Pu)O2 fuel irradiation experiment, will be presented.

14:20 - 14:40 - Montagu III

A STUDY ON THE OPTIMAL COOLING TIME OF ACTINIDE FEEDSTOCK FOR USE IN TRANSURANIC MIXED OXIDE FUELS IN CANDU REACTORS

A. C. Morreale (CNL), J. C. Luxat (McMaster University)

Transuranic actinides from spent fuel can be burned in current reactors as a mixed oxide (MOX) with natural uranium, reducing spent fuel radiation and heat loads. Detailed reactor physics analysis of transuranic MOX in CANDU (TRUMOX-CANDU) showed significant actinide conversion while maintaining operational performance. The different cooling times of spent fuel feedstock affect the MOX fuel actinide composition, which: i) alters the neutronics of the resulting TRUMOX fuel, ii) affects actinide conversion, and iii) determines end of cycle composition, dictating spent fuel radiation and heat loads. These effects are examined to find a balance between in-core performance, actinide conversion and end of cycle spent fuel properties. TRUMOX fuel compositions, dictated by the cooling time of the actinide feedstock, are evaluated with WIMS-AECL CANDU lattice cell calculations. In-core neutronics, actinide conversion ratio, and end of cycle fuel composition are examined to estimate an optimal cooling time for the actinide feedstock before use in TRUMOX fuel.

134


14:40 - 15:00 - Montagu III

PRODUCTIVE ELIMINATION OF NUCLEAR WASTE (PENW): A COMPLEMENTARY BOON FOR CANDUS AND THE CANADIAN NUCLEAR INDUSTRY

P. Ottensmeyer (University of Toronto)

Spent CANDU fuel with its substantially lower fissile content than spent LWR fuel is currently considered waste, slated for long-term permanent DGR disposal. Nevertheless, it is over 99% heavy atoms all of which can be used as fuel in fast-neutron reactors (FNRs). Such use extracts 13,400% more energy, and by splitting the constituent long-lived transuranics also eliminates their long-term radiotoxicity. FNR fuel cycling was achieved for decades elsewhere. Its adoption now for spent CANDU fuel should produce a win-win for the Canadian nuclear industry: effectively no deleterious long-term radioactive legacy, an easy justification for more CANDU reactors, and a bright future.

15:00 - 15:20 - Montagu III

NATURAL URANIUM EQUIVALENT FUEL - AN INNOVATIVE DESIGN FOR PROVEN CANDU TECHNOLOGY

F. Pineiro, K. Ho, A. Khaial, M. Boubcher, C. Cottrell, S. Kuran (Candu Energy Inc.), Z. Zhenhua, M. Zhiliang (Third Qinshan Nuclear Power Company)

The high neutron economy, on-power refuelling capability and fuel bundle design simplicity in CANDU® reactors allow for the efficient utilization of alternative fuels. Candu Energy Inc. (Candu), in collaboration with the Third Qinshan Nuclear Power Company (TQNPC), the China North Nuclear Fuel Corporation (CNNFC), and the Nuclear Power Institute of China (NPIC), has successfully developed an advanced fuel called Natural Uranium Equivalent (NUE). This innovative design consists of a mixture of recycled and depleted uranium, which can be implemented in existing CANDU stations thereby bringing waste products back into the energy stream, increasing fuel resources diversity and reducing fuel costs.

135


3B1 - Waste Management & Decommissioning 15:40-16:40 - Loyalist

Chair: Chris Hatton, Nuclear Waste Management Organization

15:40 - 16:00 CANADA’S DEEP GEOLOGICAL REPOSITORY FOR USED NUCLEAR FUEL – UPDATE ON THE SITE EVALUATION PROCESS AND INTERWEAVING OF ABORIGINAL TRADITIONAL KNOWLEDGE

B. Watts, M. Ben Belfadhel, J. A. Facella (Nuclear Waste Management Organization)

16:00 - 16:20 ASSESSMENT OF DISRUPTIVE SCENARIOS OF A CANADIAN USED FUEL REPOSITORY IN CRYSTALLINE ROCK

M. Gobien, F. Garisto, N. Hunt, E. Kremer (Nuclear Waste Management Organization)

136


Session: 3B1 - Waste Management & Decommissioning Paper Abstracts / Sommaires

15:40 - 16:00 - Loyalist

CANADA’S DEEP GEOLOGICAL REPOSITORY FOR USED NUCLEAR FUEL – UPDATE ON THE SITE EVALUATION PROCESS AND INTERWEAVING OF ABORIGINAL TRADITIONAL KNOWLEDGE

B. Watts, M. Ben Belfadhel, J. A. Facella (Nuclear Waste Management Organization)

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for the long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada’s used nuclear fuel in a Deep Geological Repository (DGR) in a suitable crystalline or sedimentary rock formation. In May 2010, the NWMO initiated a nine-step site selection process to seek an informed and willing community to host Canada’s deep geological repository. As of April 2015, twenty-two communities expressed interest in learning more about the project. This paper provides an update on the site evaluation process and describes the approach, methods and criteria used in the assessments, focusing on geological and community well-being studies. Engagement and field activities to interweave Aboriginal Traditional Knowledge with western science are also discussed.

137


16:00 - 16:20 - Loyalist

ASSESSMENT OF DISRUPTIVE SCENARIOS OF A CANADIAN USED FUEL REPOSITORY IN CRYSTALLINE ROCK

M. Gobien, F. Garisto, N. Hunt, E. Kremer (Nuclear Waste Management Organization)

The NWMO has recently extended its modelling capabilities by performing simulations for four disruptive scenarios that, to date, have not yet been examined in detail. These scenarios complement those considered in an existing postclosure safety assessment for a conceptual geological repository located in a hypothetical crystalline rock formation. The four new disruptive scenarios are: Shaft Seal Failure, Undetected Fault, Open or Poorly Sealed Borehole and Open Borehole Due to Inadvertent Human Intrusion. All simulations are based on the FRAC3DVS-OPG [1] Site-Scale Model [2]. The Site-Scale Model includes a simplified representation of the full repository and a portion of the surrounding sub-regional flow system. All transport simulations are performed with only the radionuclide I-129. Transport rates to the surface and a domestic water supply well are compared to the Reference Case results from an earlier case study documented in Reference [2].

138


3B2 - Medical Physics and Radiation Biology 15:40-16:40 - Montagu I

Chair: John Roberts (JGRchem.inc); Ruxandra Dranga (CNL)

15:40 - 16:00 THE DESIGN, CONSTRUCTION, AND COMMISSIONING OF A MULTI-USE CYCLOTRON FACILITY

S. Ho, M. Hutcheson, D. Schick-Martin (Saskatchewan Centre for Cyclotron Sciences), M. Dalzell, N. Alexander (Sylvia Fedoruk Canadian Centre for Nuclear Innovation)

16:00 - 16:20 COMMENTARY ON INHALED 239PuO2 IN DOGS — A PROPHYLAXIS AGAINST LUNG CANCER?

J. M. Cuttler (Cuttler and Associates), L. E. Feinendegen (Brookhaven National Laboratory)

16:20 - 16:40 DESIGNING A COMPUTER CODE TO CALCULATE THE COMMITTED DOSE EQUIVALENT TO INTERNAL ORGANS FOLLOWING THE INJECTION OF A RADIOPHARMACEUTICAL

Z. Keldani, R. Roman, S. Saadi, E. Nichita (UOIT)

139


Session: 3B2 - Medical Physics and Radiation Biology Paper Abstracts / Sommaires

15:40 - 16:00 - Montagu I

THE DESIGN, CONSTRUCTION, AND COMMISSIONING OF A MULTI-USE CYCLOTRON FACILITY

S. Ho, M. Hutcheson, D. Schick-Martin (Saskatchewan Centre for Cyclotron Sciences), M. Dalzell, N. Alexander (Sylvia Fedoruk Canadian Centre for Nuclear Innovation)

The Sylvia Fedoruk Canadian Centre for Nuclear Innovation in Saskatchewan is in the process of commissioning the Saskatchewan Centre for Cyclotron Sciences that is to be used for both academic research and commercial radiopharmaceutical production. The hybrid nature of this facility comes with unique challenges in satisfying both the rigid demands of pharmaceutical production while providing the necessary flexibility for academic research. In order to meet these competing demands, the Fedoruk Centre has assembled a distinct combination of skill sets and areas of expertise to operate a facility with an interdisciplinary focus.

16:00 - 16:20 - Montagu I

COMMENTARY ON INHALED 239PuO2 IN DOGS — A PROPHYLAXIS AGAINST LUNG CANCER?

J. M. Cuttler (Cuttler and Associates), L. E. Feinendegen (Brookhaven National Laboratory)

Several studies on the effect of inhaled plutonium-dioxide particulates and the incidence of lung tumors in dogs reveal beneficial effects when the cumulative alpha-radiation dose is low. There is a threshold at an exposure level of about 100 cGy for excess tumor incidence and reduced lifespan. The observations conform to the expectations of the radiation hormesis dose-response model and contradict the predictions of the Linear No-Threshold (LNT) hypothesis. These studies suggest investigating the possibility of employing low-dose alpha-radiation, such as from 239PuO2 inhalation, as a prophylaxis against lung cancer.

140


16:20 - 16:40 - Montagu I

DESIGNING A COMPUTER CODE TO CALCULATE THE COMMITTED DOSE EQUIVALENT TO INTERNAL ORGANS FOLLOWING THE INJECTION OF A RADIOPHARMACEUTICAL

Z. Keldani, R. Roman, S. Saadi, E. Nichita (UOIT)

Radiopharmaceuticals are drugs that contain radioactive isotopes and are used in the nuclear medicine field for diagnostic procedures. There is a demand for an effective software to calculate the Committed Dose Equivalent (CDE) to patients. The designed software would be a useful tool for medical professionals in the nuclear medicine field and for any patient interested in knowing the dose received following the injection of a radiopharmaceutical. The aim is to design an affordable and easy to learn tool to estimate the Committed Dose Equivalent to various organs of interest as well as the total body.

141


3B3 - Safety and Licensing (IV) 15:40-16:40 - Montagu II

Chair: Mark McIntyre (Atlantic Nuclear Inc.); Mohinder Grover (M.S. Groover and Associates)

15:40 - 16:00 DEVELOPMENT OF CANADIAN SEISMIC DESIGN APPROACH AND OVERVIEW OF SEISMIC STANDARDS

A. Usmani (Amec Foster Wheeler), T. Aziz (TSAziz Consulting Inc.)

16:00 - 16:20 PROBABILISTIC SEISMIC HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), A. Lavine (AMEC Foster Wheeler Environment & Infrastructure), J. Egan (SAGE Engineers)

16:20 - 16:40 PROBABILISTIC TSUNAMI HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), T. Alcinov, P. Roussel, A. Lavine, M. E. M. Arcos, K. Hanson, R. Youngs (AMEC Foster Wheeler Environment & Infrastructure)

142


Session: 3B3 - Safety and Licensing (IV) Paper Abstracts / Sommaires

15:40 - 16:00 - Montagu II

DEVELOPMENT OF CANADIAN SEISMIC DESIGN APPROACH AND OVERVIEW OF SEISMIC STANDARDS

A. Usmani (Amec Foster Wheeler), T. Aziz (TSAziz Consulting Inc.)

Historically the Canadian seismic design approaches have evolved for CANDU® nuclear power plants to ensure that they are designed to withstand a design basis earthquake (DBE) and have margins to meet the safety requirements of beyond DBE (BDBE). While the Canadian approach differs from others, it is comparable and in some cases more conservative.

The seismic requirements are captured in five CSA nuclear standards which are kept up to date and incorporate lessons learnt from recent seismic events.

This paper describes the evolution of Canadian approach, comparison with others and provides an overview and salient features of CSA seismic standards.

16:00 - 16:20 - Montagu II

PROBABILISTIC SEISMIC HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), A. Lavine (AMEC Foster Wheeler Environment & Infrastructure), J. Egan (SAGE Engineers)

A Probabilistic Seismic Hazard Assessment (PSHA) has been performed for the Point Lepreau Generating Station (PLGS). The objective is to provide characterization of the earthquake ground shaking that will be used to evaluate seismic safety. The assessment is based on the current state of knowledge of the informed scientific and engineering community regarding earthquake hazards in the site region, and includes two primary components—a seismic source model and a ground motion model. This paper provides the methodology and results of the PLGS PSHA. The implications of the updated hazard information for site safety are discussed in a separate paper.

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16:20 - 16:40 - Montagu II

PROBABILISTIC TSUNAMI HAZARD ASSESSMENT FOR POINT LEPREAU GENERATING STATION

D. Mullin (NB Power, Point Lepreau Generating Station), T. Alcinov, P. Roussel, A. Lavine, M. E. M. Arcos, K. Hanson, R. Youngs (AMEC Foster Wheeler Environment & Infrastructure)

In 2012 the Geological Survey of Canada published a preliminary probabilistic tsunami hazard assessment in Open File 7201 that presents the most up-to-date information on all potential tsunami sources in a probabilistic framework on a national level, thus providing the underlying basis for conducting site-specific tsunami hazard assessments. However, the assessment identified a poorly constrained hazard for the Atlantic Coastline and recommended further evaluation. As a result, NB Power has embarked on performing a Probabilistic Tsunami Hazard Assessment (PTHA) for Point Lepreau Generating Station. This paper provides the methodology and progress or hazard evaluation results for Point Lepreau G.S.

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Although every effort has been made to make this Pocket Program complete and accurate, there may be instances where information is

overlooked or was not ready at the time of publication. In the event that you find any errors with your name, affiliation or abstract, please send an

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For the most up-to-date program schedule, please go to:http://cnsconference2015.org/proceedings

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35th Annual CNS Conference 39th CNS/CNA Student Conference

Hilton Saint John / Saint John Trade and Convention Center 1 Market Square, Saint John, New Brunswick E2L 4Z6

May 31 - June 3, 2015 147

SAINT JOHN TRADE & CONVENTION CENTRE MAP

Stairs to Kennebecasis Room at Hilton Hotel

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Leverage our expertise and facilities to improve the competitiveness of your organization. For more information visit www.cnl.ca.

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