Zobrazeno 1 - 10
of 160
pro vyhledávání: '"Jinya Katsuyama"'
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00567-19-00567 (2020)
Non-destructive examinations (NDEs) have an important role in assurance of the structural integrity of nuclear components including pipe lines. NDEs are performed for welds in piping in accordance with the rules, which prescribe the requirements of N
Externí odkaz:
https://doaj.org/article/bdccdb0f5a634885a2d2f77a0e395f51
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00560-19-00560 (2020)
Since the Fukushima Daiichi nuclear power plant accident, we have been developing a failure evaluation method that considers creep damage mechanisms using detailed three-dimensional finite element analysis model of lower head including penetration, s
Externí odkaz:
https://doaj.org/article/50bae0b989b147d69ad24f686800aff9
Autor:
Kai LU, Jinya KATSUYAMA, Yinsheng LI, Yuhei MIYAMOTO, Takatoshi HIROTA, Yu ITABASHI, Masaki NAGAI, Masahide SUZUKI, Yasuhiro KANTO
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00573-19-00573 (2020)
Probabilistic fracture mechanics (PFM) is considered a promising methodology in assessing the integrity of structural components in nuclear power plants because it can rationally represent the influence parameters in their probabilistic distributions
Externí odkaz:
https://doaj.org/article/a0cb1ac09d11407d8a3bd69bd0f2080e
Autor:
Yoshihito YAMAGUCHI, Jinya KATSUYAMA, Yoshiyuki NEMOTO, Yoshiyuki KAJI, Hiroyuki YOSHIDA, Yinsheng LI
Publikováno v:
Mechanical Engineering Journal, Vol 4, Iss 6, Pp 15-00694-15-00694 (2017)
After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthquake and Tsunami, we have been developing an analysis method considering creep damage mechanisms based on three-dimensional analysis in order to estimat
Externí odkaz:
https://doaj.org/article/c345bbd22c2e4c439d6254c95639cfe5
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:
Mechanical Engineering Journal, Vol 3, Iss 3, Pp 15-00682-15-00682 (2016)
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RPV) by relocated molten core is judged using simple models such as temperature and/or stress criteria. However, it is difficult to assess rupture behav
Externí odkaz:
https://doaj.org/article/b70b2755dee14717935b96e45be7c822
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 3, Pp 15-00619-15-00619 (2016)
An iodine-sulfur process based thermochemical water-splitting (IS process) for hydrogen production has been developed by JAEA as application of a high-temperature gas cooled reactor. The IS process includes a severe corrosion environment which is mad
Externí odkaz:
https://doaj.org/article/dc466d523eb943b5a65f7f6cdf6fd61b
Autor:
Keiko Iwata, Yoosung Ha, Masaki Shimodaira, Yoshihiro Okamoto, Mitsunori Honda, Yutaka Nishiyama, Jinya Katsuyama, Hisashi Takamizawa
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 511:143-152
Irradiation embrittlement is one of the most important phenomena in the structural integrity assessment for long-term operated reactor pressure vessels (RPVs). The causes of the irradiation embrittlement of RPVs are the formation of solute clusters a
Publikováno v:
Journal of Pressure Vessel Technology. 145
The fracture toughness in the heat-affected zone (HAZ), which is located under the weld overlay cladding on the inner surface of the reactor pressure vessel (RPV), was evaluated by considering the inhomogeneous microstructures of the HAZ. In this reg
Publikováno v:
Fatigue & Fracture of Engineering Materials & Structures. 44:3399-3415