Japanese Activities Concerning Nuclear Codes and Standards—Part I

Author:

Asada Yasuhide1

Affiliation:

1. Thermal and Nuclear Power Engineering Society, Terayama Pacific Bldg, 1-23-11 Toranomon, Minato-ku, Tokyo 105-0001 Japan

Abstract

This series of papers has been issued to give general views on recent Japanese activities related to nuclear codes and standards. Part I of the series includes an overview, a discussion of administrative and design aspects related to new methods of evaluating the integrity of components, that is, piping seismic rules based on ratcheting fatigue, a fracture toughness equation for vessel materials, an extension of the Ke factor based on elastic follow-up, a discussion of high cycle thermal fatigue, and a three-dimensional finite element method elastic-plastic analysis procedure.

Publisher

ASME International

Subject

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

Reference43 articles.

1. Japan Electric Association, 1984, “Technical Guidelines for Aseismic Design of Nuclear Power Plants: Supplement Allowable Stress, Classification,” JEAG 4601: Supplement.

2. Japan Electric Association, 1987, “Technical Guidelines for Aseismic Design of Nuclear Power Plants,” JEAG 4601.

3. Japan Electric Association, 1991, “Technical Guidelines for Aseismic Design of Nuclear Power Plants: Supplement,” JEAG 4601, Supplement edition.

4. Park, Y. J., and Hofmayer, C. H., NUREG/CR-6241 (BNL-NUREG-52422) 1994, “Technical Guidelines for Aseismic Design of Nuclear Power Plants,” Translation of JEAG 4601-1987.

5. EPRI, 1993, “Piping and Fitting Reliability Program, Vol. 1, Project Summary.”

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