原子力維持規格における配管許容欠陥に関する考察

（日米規格の比較と今後の課題）

抄録

Allowable crack is one of the most important concepts to maintain the structural integrity of nuclear power plant components and it is introduced in the Fitness-For-Service codes in US and Japan. This paper shows the comparison of ASME Code Section XI on the allowable crack for nuclear piping with JSME code and also presents some new proposals, including future issues.