Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Author:

Takaya Shigeru1,Asayama Tai1,Yada Hiroki1,Thomas Roberts A.2,Schaaf Frank J.3

Affiliation:

1. Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan

2. MPR Associates, Inc., 2 Wilderness Way, Chadds Ford, PA 19317-9175

3. Sterling Refrigeration Corp., 648 Holt Road, Webster, NY 14580

Abstract

Abstract Inservice inspection rules for liquid-metal cooled plants were historically provided by Section XI, Division 3 of the ASME Boiler and Pressure Vessel Code. However, some parts of the Code, such as acceptance standards for the examination of class 1 and 2 components remained as being in the course of preparation. Although no major revisions were made to Division 3 since the first issue in 1980, a newly developed and published Code Case N-875 now provides alternative examinations to the methods previously contained in Division 3. The Code Case was developed using the System Based Code (SBC) concept pursuing rationalization of codes and standards based on reliability targets throughout a plant's service life. In this paper, an overview of the Code Case is presented. The technical foundation to establish the applicability of these alternative examinations as delineated in the Code Case consists of stage I and II evaluations with compensating individual considerations. Stage I is a structural integrity evaluation without the contribution of inservice inspections, while stage II is evaluation of the detectability of a postulated flaw. Not only conventional direct detection methods, but also indirect detection methods are permitted to be employed through the stage II evaluation. Furthermore, the detailed evaluation procedures are illustrated through the application of the Code Case's evaluation criteria to the primary heat transport piping system of a prototype sodium-cooled fast breeder reactor in Japan, specifically Monju.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference13 articles.

1. Boiler and Pressure Vessel Code, Section XI, Division 3, Rules for Inspection and Testing of Components of Liquid-Metal-Cooled Plants;ASME,2001

2. Boiler and Pressure Vessel Code, Code Cases, Nuclear Components, N-875 Alternative Inservice Inspection Requirements for Liquid-Metal Reactor Passive Components;ASME,2017

3. System Based Code—Principal Concept,2002

4. System Based Code—Basic Structure,2002

5. An Introduction of MONJU,2004

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1. ARKADIA—For the Innovation of Advanced Nuclear Reactor Design;Journal of Nuclear Engineering and Radiation Science;2022-06-15

2. Key technologies for future sodium-cooled fast reactors;Sodium-cooled Fast Reactors;2022

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