Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Riichiro Okawa"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00496-23-00496 (2024)
In severe accidents in light-water reactors, the core melt, which falls to the bottom of the containment vessel, is expected to be cooled in the retained water. The particulate debris is generated after the molten material falls from the pressure ves
Externí odkaz:
https://doaj.org/article/e8a46409c2584d38884478728421c165
Autor:
Takahiro ARAI, Atsushi UI, Masahiro FURUYA, Riichiro OKAWA, Tsugumasa IIYAMA, Shota UEDA, Kenetsu SHIRAKAWA, Kazuaki KITO
Publikováno v:
Mechanical Engineering Journal, Vol 8, Iss 4, Pp 21-00001-21-00001 (2021)
The void fraction distribution of a fuel rod bundle in a boiling water reactor is a critical parameter for accurately predicting the optimal thermal margin in the design of a reactor core. The rod bundle configuration, such as a part-length rod (PLR)
Externí odkaz:
https://doaj.org/article/06c6b44fd39c42b1aeae9ba64afff1dc
Autor:
Tsugumasa Iiyama, Masahiro Furuya, Takahiro Arai, Atsushi Ui, Riichiro Okawa, Kenetsu Shirakawa, Taro Shimada
Publikováno v:
Journal of Nuclear Science and Technology. 59:1478-1486
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fde34953cf4f290d854062d7a2499c50
https://doi.org/10.1080/00223131.2022.2064357
https://doi.org/10.1080/00223131.2022.2064357
Autor:
Atsushi Ui, Tetsuhiro Ozaki, Takahiro Arai, Masahiro Furuya, Riichiro Okawa, Tsugumasa Iiyama, Shota Ueda
Publikováno v:
Multiphase Science and Technology. 34:1-23
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5eedaba49073cfda604ce447b698928
https://doi.org/10.1615/multscientechn.2022043255
https://doi.org/10.1615/multscientechn.2022043255
Publikováno v:
Nuclear Engineering and Design. 402:112103
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5ec60c80c85d7d18eec98655217b42c
https://doi.org/10.1016/j.nucengdes.2022.112103
https://doi.org/10.1016/j.nucengdes.2022.112103
Publikováno v:
Annals of Nuclear Energy. 129:207-213
Boiling of sea water may occur in a pressure vessel of light water (nuclear) reactors to flood the nuclear fuel as an accident management procedure. Another salt water is borated water, which will be injected into the reactor core as a neutron absorb
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ceca669c63294630af51467cf90378b1
https://doi.org/10.1016/j.anucene.2019.01.043
https://doi.org/10.1016/j.anucene.2019.01.043
Autor:
Riichiro Okawa, Masahiro Furuya
Publikováno v:
Nuclear Engineering and Design. 346:97-111
Numerical analyses were conducted to replicate several tests for simulating a double-ended cold-leg large break loss-of-coolant accident (LBLOCA) in the Loss-of-Fluid Test (LOFT) using the TRACE (version 5/patch level 4) code. Analytical results by t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb6bb98097a8bb9eddfeba8d870337f4
https://doi.org/10.1016/j.nucengdes.2019.03.003
https://doi.org/10.1016/j.nucengdes.2019.03.003
Publikováno v:
Nuclear Engineering and Design. 341:38-45
As an accident management procedure of light water (nuclear) reactors which are situated along sea shore, sea water will be injected into the reactor pressure vessel to flood the nuclear fuel which is heated by residual heat. Another salt water is bo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7374c120f8c9c6b0a6a8a8bda9555b7a
https://doi.org/10.1016/j.nucengdes.2018.10.012
https://doi.org/10.1016/j.nucengdes.2018.10.012
Autor:
Kazuaki Kito, Takahiro Arai, Tsugumasa Iiyama, Kenetsu Shirakawa, Masahiro Furuya, Riichiro Okawa, Shota Ueda, Atsushi Ui
Publikováno v:
Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.
A boiling experiment was conducted to acquire a three-dimensional void fraction distribution in a rod bundle with part length rods. The test section was a 5 × 5 heated rod bundle that partially simulated a BWR rod bundle, and three PLRs were arrange
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::10c5e2e3164d2ab11a2b11ecbd15a06d
https://doi.org/10.1115/icone2020-16759
https://doi.org/10.1115/icone2020-16759
Publikováno v:
Nuclear Engineering and Design. 377:111155
We have established an experimental system to visualize a droplet flow in a simulated BWR fuel sub-channel optically and measure the diameter and velocity of droplet after passing through a spacer. For representative spacers of ferrule and grid type,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::657d3997994493ee6cf863a77621bd43
https://doi.org/10.1016/j.nucengdes.2021.111155
https://doi.org/10.1016/j.nucengdes.2021.111155