Ageing management considerations in mechanical codes and standards

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.

Objectives

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).

Scope and sessions

High-level national and international experts from a wide range of stakeholders shared their experiences and views during the four sessions of the workshop:

  1. National regulatory requirements related to ageing phenomena on reactor coolant pressure boundary;
  2. Code requirements on RCPB to address/prevent ageing;
  3. Operation experiences related to ageing phenomena on RCPB;
  4. Challenges of ageing phenomena in C&S applied to SMRs/AMRs
Programme

Day 1 - 28 June 2023, from 09:00

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

Session 2: Discussion on code requirements on RCPB to address/prevent ageing phenomena

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

End of Day 1

 

Day 2 - 29 June 2023, from 09:00

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

Session 4: Challenges of ageing phenomena in C&S applied to SMRs/AMRs

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