Overview of JSME flaw evaluation code for nuclear power plants

Citation
H. Kobayashi et K. Kashima, Overview of JSME flaw evaluation code for nuclear power plants, INT J PRES, 77(14-15), 2000, pp. 937-944
Citations number
6
Categorie Soggetti
Mechanical Engineering
Journal title
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
ISSN journal
03080161 → ACNP
Volume
77
Issue
14-15
Year of publication
2000
Pages
937 - 944
Database
ISI
SICI code
0308-0161(200012)77:14-15<937:OOJFEC>2.0.ZU;2-G
Abstract
A Japanese flaw evaluation code for nuclear power plant components has been developed at: the Japan Society of Mechanical Engineers (JSME). The code p rescribes methods for the evaluation of flaws, which are detected during in service inspection for pressure vessels and pipes in nuclear power plants. This paper describes the basic dow chart, methods of evaluation and allowab le flaw sizes for acceptance standards and criteria, including comparisons with the ASME Code Section XI. (C) 2001 Elsevier Science Ltd. All rights re served.