Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Chikashi Shitara"'
Publikováno v:
Volume 1: Codes and Standards.
A fracture assessment method for piping of BWR reactor internals with a circumferential crack is described in the JSME Code, Rules on Fitness-for-Service for Nuclear Power Plants 2004 Edition. According to this code, limit load is calculated assuming
Autor:
Jun Mizutani, Shunichi Suzuki, Tsuneo Futami, Kazuyoshi Yonekura, Chikashi Shitara, Minoru Masuda, Katsuhiko Kumagai
Publikováno v:
Residual Stress, Fracture, and Stress Corrosion Cracking.
Through inspections of Japanese boiling water reactors (BWRs) from 2002, a high occurrence rate of Inter Granular Stress Corrosion Cracking (IGSCC) was confirmed in core shrouds and re-circulation (PLR) pipings made of low-carbon (L-grade) stainless
Publikováno v:
Pressure Vessel and Piping Codes and Standards.
The ASME Code for seismic design of piping system was revised in 1994 based on evaluation of pipe component test results submitted by the Piping and Fitting Dynamic Reliability Program (PFDRP). PFDRP indicated piping component failure to result in mo
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2007:222-223
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2007:244-245
Publikováno v:
The proceedings of the JSME annual meeting. :435-436
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2008:OS0308-1
Publikováno v:
TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A. 50:165-173