Zobrazeno 1 - 10
of 32
pro vyhledávání: '"Yoshiyuki NEMOTO"'
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00450-19-00450 (2020)
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained
Externí odkaz:
https://doaj.org/article/e952e62ca66a4f80b94d238772768d5d
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
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:
Journal of Nuclear Science and Technology. 60:320-333
Autor:
Takafumi Narukawa, Keietsu Kondo, Yuki Fujimura, Kazuo Kakiuchi, Yutaka Udagawa, Yoshiyuki Nemoto
Publikováno v:
Journal of Nuclear Materials. 582:154467
Publikováno v:
Volume 4A: Materials and Fabrication.
To assess rupture behavior of the lower head of reactor pressure vessel in boiling-water-type nuclear power plants due to severe accident like Fukushima Daiichi, we have been developing an analysis method based on coupled analysis of three-dimensiona
Publikováno v:
Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00450-19-00450 (2020)
In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained
Autor:
Toru Kanazawa, Keietsu Kondo, Yoshiyuki Kaji, Yoshiyuki Nemoto, Kazuo Nakashima, Chihiro Ogawa, Masayuki Tojo
Publikováno v:
Journal of Nuclear Materials. 488:22-32
The authors previously conducted thermogravimetric analyses on zircaloy-2 in air. By using the thermogravimetric data, an oxidation model was constructed in this study so that it can be applied for the modeling of cladding degradation in spent fuel p
Autor:
Hiroyuki Yoshida, Yinsheng Li, Yoshiyuki Nemoto, Jinya Katsuyama, Yoshihito Yamaguchi, Yoshiyuki Kaji
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
Publikováno v:
Zairyo-to-Kankyo. 66:180-187