Inspection and evaluation of defects on the Codes for Nuclear Power Generation Facilities
Creators
- 1. Central Research Institute of Electric Power Industry, Komae, Tokyo (Japan)
- 2. Central Research Institute of Electric Power Industry, Materials Science Research Laboratory, Yokosuka, Kanagawa (Japan)
Description
An outline of inspection and evaluation of defects on the JSME S-NA1-2004 and the performance demonstration (PD) system is stated. JSME S-NA1-2004 consists of three chapters such as inspection, evaluation, maintenance and exchange. The first chapter, inspection, contains the standard inspection and separate inspection. The second chapter, evaluation, is constructed by definition, types, methods and evaluation of defects. In the third chapter, the inspection and evaluation are explained in detail. The progress analyses of fatigue crack of ferrite vessel and tube are studied. The evaluation methods of fatigue crack and fracture are the same as ones of the ASME codes. The PD system in Japan is explained. Application of the codes to No 3 and No 5 of Kashiwazaki-Kariwa Nuclear Power Station has been approved. With particular reference to the ASME codes, working out of the codes in Japan is described. (S.Y.)
Additional details
Publishing Information
- Journal Title
- Kensa Gijutsu
- Journal Volume
- 13
- Journal Issue
- 7
- Journal Page Range
- p. 10-16
- ISSN
- 1342-9825
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39089503
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRACKS; DEFECTS; DESTRUCTIVE TESTING; EVALUATION; IN-SERVICE INSPECTION; JAPAN; REACTOR MAINTENANCE; REACTOR SAFETY; STANDARDS; STRESS CORROSION; ULTRASONIC TESTING
- Descriptors DEC
- ACOUSTIC TESTING; ASIA; CHEMICAL REACTIONS; CORROSION; DEVELOPED COUNTRIES; INSPECTION; MAINTENANCE; MATERIALS TESTING; NONDESTRUCTIVE TESTING; SAFETY; TESTING