Zobrazeno 1 - 10
of 37
pro vyhledávání: '"Takatoshi HIROTA"'
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 86, Iss 882, Pp 19-00308-19-00308 (2020)
The Japan Electric Association code, JEAC 4206-2016 specifies a procedure for assessment of a reactor pressure vessel integrity against pressurized thermal shock (PTS) events which postulates a semi-elliptical flaw (10 mm in depth x 60 mm in length)
Externí odkaz:
https://doaj.org/article/a27283b7ee5a4c59a7d6ad2f480d5470
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:
Takatoshi HIROTA, Kentaro YOSHIMOTO
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 85, Iss 873, Pp 18-00369-18-00369 (2019)
The reactor pressure vessel is made of ferritic low alloy steel, which has fracture behaviors that include ductile to brittle transition temperature and decrease of fracture toughness in the beltline region of the reactor pressure vessel steel due to
Externí odkaz:
https://doaj.org/article/068c8225cae34da289ad48151c406d39
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b6b221986f488bbbbabff6d7700c419
https://doi.org/10.1115/pvp2022-84554
https://doi.org/10.1115/pvp2022-84554
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9cbf3e421210677076adc5bc34a87c78
https://doi.org/10.1115/pvp2022-84186
https://doi.org/10.1115/pvp2022-84186
Publikováno v:
Transactions of the JSME (in Japanese). 86:19-00308
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4f72c01d45014272e46cf670cccbd301
https://doi.org/10.1299/transjsme.19-00308
https://doi.org/10.1299/transjsme.19-00308
Autor:
Yasuhiro Kanto, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Kai Lu, Takatoshi Hirota, Yuhei Miyamoto, Yinsheng Li, Jinya Katsuyama
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::1f90cac9fe3914fb73f9647b1d0303eb
https://www.jstage.jst.go.jp/article/mej/7/3/7_19-00573/_pdf/-char/en
https://www.jstage.jst.go.jp/article/mej/7/3/7_19-00573/_pdf/-char/en
The Beremin model can handle both the plastic constraint effect and data scatter for brittle fracture. Many researchers have been investigating its applicability for more than 30 years and are still discussing the temperature dependence of Weibull pa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3ab2850ee035ffbb59f016a461e89119
https://doi.org/10.1115/1.0000229v
https://doi.org/10.1115/1.0000229v
Autor:
Hisashi Takamizawa, Takatoshi Hirota, Yutaka Nishiyama, Tohru Tobita, Kuniki Hata, Y. Chimi, Keiko Iwata
Publikováno v:
Volume 1: Codes and Standards.
The crack arrest fracture toughness, KIa, values for highly-irradiated reactor pressure vessel (RPV) steels are estimated according to the linear relationship between crack arrest toughness reference temperature, TKIa, and the temperature correspondi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::41d4aba2dc14266988df9686fd7e9d04
https://doi.org/10.1115/pvp2021-61893
https://doi.org/10.1115/pvp2021-61893