Published June 1999
| Version v1
Journal article
Maintenance standards and defects evaluation of pressure equipment
Description
Defects evaluation which was the most important object in fracture dynamics was concretely described. A defects evaluation method is regulated in Sec. XI, ASME Boiler and Pressure Vessel Code. This method is widely applied in the world not only to nuclear power plant, but also to general appliances. In Japan, technical standard on maintenance of the nuclear power plant components is also recently prepared by using Sec. XI of ASME standard for a model. In this technical maintenance standard, a defects evaluation method in response to actual condition in Japan is regulated. Here are described concretely on defects evaluation by using the defects evaluation method of maintenance standard in Japan for a base. (G.K.)
Additional details
Publishing Information
- Journal Title
- Haikan Gijutsu
- Journal Volume
- 41
- Journal Issue
- 7
- Journal Page Range
- p. 1-8
- ISSN
- 0385-9894
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30044906
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRACK PROPAGATION; DEFECTS; FRACTURE MECHANICS; JAPAN; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PIPES; PRESSURE VESSELS; SAFETY STANDARDS
- Descriptors DEC
- ASIA; CONTAINERS; DEVELOPED COUNTRIES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; STANDARDS; THERMAL POWER PLANTS