Zobrazeno 1 - 10
of 106
pro vyhledávání: '"Kiminobu HOJO"'
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 87, Iss 903, Pp 21-00149-21-00149 (2021)
A procedure for application of finite element analyses (FEAs) for the limit load assessment was investigated for the fitness-for-service code for nuclear facility by the Japan Society of Mechanical Engineers. The current code prescribes the equations
Externí odkaz:
https://doaj.org/article/d0ca9f2eb469419eb941f312369bca33
Publikováno v:
Mechanical Engineering Journal, Vol 4, Iss 4, Pp 16-00642-16-00642 (2017)
The current JSME rules on Fitness-for-Service only applies the Elastic Plastic Fracture Mechanics (EPFM) method, including the two-parameters method for flaw evaluation of cast stainless steel (CASS) pipes, while plastic collapse is expected to occur
Externí odkaz:
https://doaj.org/article/642130283d154e64abac561f6e649705
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 82, Iss 841, Pp 16-00263-16-00263 (2016)
Fracture strength of cracked pipes made of moderate toughness materials is derived using J-integral value, which represents the driving force for fracture, and J-R curve, which corresponds to the material strength. However, in practical applications,
Externí odkaz:
https://doaj.org/article/6ecca0e2fe454c0393dbca8d84984000
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
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 80, Iss 818, Pp SMM0293-SMM0293 (2014)
Thermal fatigue may occur in a pipe with high temperature stratified flow. To avoid the fatigue damage by the stratified flow, it is important to know a history of temperature and thermal stress distribution in the pipe. This paper describes a heat c
Externí odkaz:
https://doaj.org/article/f8f2b90cf3ff4817a5ce6207cf588934
Publikováno v:
Volume 4A: Materials and Fabrication.
The European project “Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)” is aiming to achieve a reasonable balance between safety and long term operation of nuclear reactor pressure coolant boundary systems. In
Autor:
Kiminobu Hojo, Takatoshi Hirota, Yasuto Nagoshi, Takuya Fukahori, Kimihisa Sakima, Mitsuru Ohata, Fumiyoshi Minami
Publikováno v:
Volume 1: Codes and Standards.
In order to predict fracture behavior of a structure with low constraint, tensile fracture tests using flat plate specimens with a surface flaw were performed at −80°C and −120°C in the ductile-brittle transition temperature (DBTT) region. The
Autor:
Kiminobu Hojo, Satoshi Kumagai
Publikováno v:
Volume 4A: Materials and Fabrication.
Fatigue crack growth calculation method beyond ΔK in codes and standards, like ASME Sec. XI or JSME rules for Fitness for Service has not been established even in Mode I. In the FDF-II Subcommittee of the nuclear research committee of the Japan Weld
Publikováno v:
Transactions of the JSME (in Japanese). 87:21-00149