Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Yasukazu Takada"'
Autor:
Kiminobu HOJO, Shotaro HAYASHI, Wataru NISHI, Masayuki KAMAYA, Jinya KATSUYAMA, Koichi MASAKI, Masaki NAGAI, Toshiki OKAMOTO, Yasukazu TAKADA, Shinobu YOSHIMURA
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 4, Pp 16-00083-16-00083 (2016)
Performance demonstration certification of non-destructive inspection for cast stainless steel (CASS) has been planned but the target flaw depth to be detected has not been determined yet in Japan. The target flaw size is closely connected to the all
Externí odkaz:
https://doaj.org/article/6b8f36aec73649b380916388423e7ae4
Autor:
Toshiki Okamoto, Shinobu Yoshimura, Masaki Nagai, Yasukazu Takada, Wataru Nishi, Jinya Katsuyama, Kiminobu Hojo, Shotaro Hayashi, Koichi Masaki, Masayuki Kamaya
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 4, Pp 16-00083-16-00083 (2016)
Performance demonstration certification of non-destructive inspection for cast stainless steel (CASS) has been planned but the target flaw depth to be detected has not been determined yet in Japan. The target flaw size is closely connected to the all
Publikováno v:
Volume 1A: Codes and Standards.
In order to develop new design fatigue curves for austenitic stainless steels, carbon steels and low alloy steels and a new design fatigue evaluation method that are rational and have a clear design basis, the Design Fatigue Curve (DFC) subcommittee
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :ICONE23-1
Publikováno v:
Volume 1: Codes and Standards.
It is important to evaluate environmental fatigue for establishing long-term maintenance plans as part of Plant Life Management (PLM) activities for nuclear power plants. In Japan, the former MITI requested the utilities in 2000 to use “The Guideli
Autor:
Hiroshi Yokota, Hideo Kobayashi, Keisuke Kitsukawa, Koichi Murayama, Hiroshi Ueda, Yasukazu Takada
Publikováno v:
Pressure Vessel and Piping Codes and Standards.
As one of the Codes for Nuclear Power Generation Facilities, “Rules on Protection Design against Postulated Pipe Rupture for Nuclear Power Plants (JSME S ND1-2002)” has been developed by the JSME Committee on Power Generation Facility Codes from