Session: CS-01-02: Structural Integrity of Pressure Components

Paper Number: 84707

84707 - Introduction of Standard Development Organization (Sdo) Convergence Board 

The Multinational Design Evaluation Programme (MDEP) Code Comparison Project was initiated in late 2006 in response to a request by the MDEP Codes and Standards Working Group (CSWG) consisted of international nuclear regulatory bodies.

The CSWG requested the various Standard Development Organizations (SDOs) to develop a comparison of their codes & standards for Nuclear Power Plant Class 1 components. “Code Comparison Report for Class 1 Nuclear Power Plant Components” (STP-NU-051-1) was published in 2012. The SDOs understood the necessity of their collaboration through this project.

So, SDO Convergence Boards was established in February 2013. The SDO Convergence Board will facilitate the following objectives for Nuclear Power Plant Codes and Standards: 1) Limit divergence on individual requirements, 2) Achieve harmonization on individual requirements, where realistic and practical.

The SDO Convergence Board will collaborate with Working Group on Codes and Standards in Committee on Nuclear Regulatory Activities (CNRA), WNA CORDEL and other global stakeholders to identify and facilitate implementation of activities leading to nuclear code convergence and minimization of code divergence.

The SDO Convergence Board discussed several topical items in an early stage. In recent years, the board sets “Three-year Work Plan” to clarify the topics, are sharing the information of each SDO and are collaborating.

Presenting Author: Seiji Asada Mitsubishi Heavy Industries, Ltd.

Presenting Author Biography: - Graduated from Kobe University in March 1987 <br/>- Master’s degree from Kobe University in March 1989<br/>- PhD from Kobe University in March 2009<br/>- Joined Mitsubishi Heavy Industries in April 1989.<br/>- Since joined in Mitsubishi heavy Industries, I have been in charge of the designing of Reactor Pressure Vessels. Especially I have made a lot of effort at stress analysis, fatigue analysis, irradiation embrittlement issue of RPVs, fracture mechanics, and so on. <br/>- Member: [ASME Code Committee] BPV III, SG on Component Design, WG on Environmental Fatigue Evaluation Method<br/>[JSME] Subcommittee on Nuclear, SG on Design and Construction, SG on Fatigue Evaluation, and so on.

Authors: