The NEA in collaboration with the Japanese Nuclear Regulatory Authority (NRA) hosted an international workshop on 28-29 June 2023 on the topic of Ageing management considerations in mechanical codes and standards.
The objectives of the workshop were to provide better understanding of the global framework and to initiate discussion between stakeholders to enable a better consideration of ageing phenomena in codes and standards. The workshop brought together regulators and stakeholders, including representatives from the industry and other international organisations, to share information and discuss the challenges related to ageing phenomena in mechanical codes and standards, for both existing fleet but also for nuclear new builds and small modular reactors (SMRs).
High-level national and international experts from a wide range of stakeholders shared their experiences and views during the four sessions of the workshop:
Welcome and registration | |
Opening Rremarks | Tomoya ICHIMURA (NRA, Japan) Seiji ASADA (MHI) |
Session 1: Comparison of national regulatory requirements related to ageing phenomena on reactor coolant pressure boundary (RCPB) | |
Introduction |
David Rudland (US NRC) |
Regulatory requirements in Korea |
Sangmin Lee (KINS, Korea) |
Regulatory requirements in Czech Republic |
Jolana Rydlova (SUJB, Czech Republic) |
Regulatory requirements in Japan |
Haruko Sasaki (NRA, Japan) |
Regulatory requirements in France |
Rachel Vaucher (ASN, France) |
Regulatory requirements in United States |
David Rudland (US NRC) |
Q/A session and panel discussion |
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Session 2: Discussion on code requirements on RCPB to address/prevent ageing phenomena |
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Introduction |
Ronan TANGUY (World Nuclear Association) |
ASME Code Requirements for Fatigue |
Paul DONAVIN (ASME) |
Outline of JSME rules on fitness for service for nuclear power plants |
Dr Kiminobu Hojo (Mistubishi Heavy Industry) |
Initiatives of Japan on standardising new findings on ageing management |
Pr Kenta Murakami (Tokyo University) |
Code Requirements for Managing Aging of Pressure Boundary Components of CANDU Reactors in Canada |
Mr Suqiang XU (CNSC, Canada) |
Experience on the ageing phenomena with mechanical design |
Mr Jongin Kim (Doosan, Republic of Korea) |
Q/A session and Panel Discussion |
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End of Day 1 |
Welcome and registration | |
Session 3: OPEX related to ageing phenomena on RCPB | |
Introduction |
Yinsheng Li (JAEA, Japan) |
SCC in France |
Rachel VAUCHER (ASN, France) |
SCC in Japan |
Takumi Terachi - ATENA (KEPCO) |
SCC Growth Rate Behavior of Stainless Steels in PWR Primary Water Environments |
Do Jun Shim (EPRI) |
Fatigue Phenomena Experience |
Paul R. Donavin (Becht Engineering) |
Integrity Assessment of Reactor Pressure Vessel Against Irradiation Embrittlement in Japan |
Takatoshi Hirota (Mitsubishi Heavy Industry) |
Q/A session and Panel Discussion |
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Session 4: Challenges of ageing phenomena in C&S applied to SMRs/AMRs |
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Introduction |
Mr Suqiang XU (CSNC, Canada) |
Degradation of Materials for High Temperature Small Modular Reactors | Dr. Suraj Persau (Queen's university) |
Materials Ageing Challenges for licensing advanced nuclear reactors | Dr. Suqiang XU (CNSC) |
Aging Management Considerations for Advanced SMRs and Non-LWR Reactors |
Mr Chris WAX (EPRI) |
Closing session: Harmonisation discussion | |
Panel discussion | |
Conclusion | Dr Sangmin LEE (KINS, Republic of Korea) |
End of Day 2 |