Zobrazeno 1 - 10 of 16 pro vyhledávání: '"Atsushi Ui"'
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Akademický článek
Void fraction distribution in a rod bundle with part-length rods via high-energy X-ray computed tomography
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
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7
High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures
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
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8
Measurement of forced convection subcooled boiling flow and rod surface temperature distribution
Autor: Kenetsu Shirakawa, Masahiro Furuya, Takahiro Arai, Atsushi Ui
Publikováno v: Nuclear Engineering and Design. 381:111323
In order to obtain high-resolution data for modelling of boiling two-phase flow and its validation, we designed and constructed a test loop with a vertical annulus flow path and conducted subcooled boiling experiments to investigate subcooled bubble
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::cdd06438c274738182e36b296e3dba33
https://doi.org/10.1016/j.nucengdes.2021.111323
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9
Void fraction distribution in a rod bundle with part-length rods via high-energy X-ray computed tomography
Autor: Kenetsu Shirakawa, Atsushi Ui, Tsugumasa Iiyama, Kazuaki Kito, Shota Ueda, Takahiro Arai, Masahiro Furuya, Riichiro Okawa
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::09427da8e640f874dcc77cd2fdd439f9
https://www.jstage.jst.go.jp/article/mej/8/4/8_21-00001/_pdf/-char/en
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10
Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 1 — Parametric Study on Fukushima-Daiichi Unit-2
Autor: Kenichi Kanda, Yoshihisa Nishi, Kazuma Abe, Satoshi Nishimura, Koichi Nakamura, Masahiro Furuya, Atsushi Ui
Publikováno v: Volume 6B: Thermal-Hydraulics and Safety Analyses.
Accident analyses of the Fukushima-Daiichi unit-2 nuclear power plant were performed with MAAP (Modular Accident Analysis Program) version 5.03. We assumed RCIC, SRV operation and alternative water injection in order to reproduce the measured pressur
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::25a76b5dd2bdf866d874191c9d6fc2d8
https://doi.org/10.1115/icone26-82129
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