Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Akehiko Hoshide"'
Autor:
Akira INOUE, Hiroshi HAYASHI, Masahiko KITAMURA, Tohru MITSUTAKE, Shinichi MOROOKA, Jiro KIMURA, Akehiko HOSHIDE, Noboru SAITOH, Nobuaki ABE, Kenji ARAI, Shigeo EBATA, Seiichi KOMURA, Satoshi NAKAMURA
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 40:784-797
Nuclear Power Engineering Corporation (NUPEC) has completed the proving test for thermal-hydraulic performance of high burnup 8×8 fuel assembly. The high-burnup 8×8 fuel is a new type of BWR fuel assembly. New concepts such as ferrule type spacer a
Publikováno v:
JAPANESE JOURNAL OF MULTIPHASE FLOW. 12:144-150
High critical-power fuel assemblies are needed for boiling water reactors to increase the thermal safety margin of the reactor core. There are seven spacers supporting the fuel rods in a BWR fuel assembly, and it is well known that the critical power
Autor:
Takao ISHIZUKA, Akira INOUE, Tatuo KUROSU, Toshimasa AOKI, Masanobu FUTAKUCHI, Makoto YAGI, Shinichi MOROOKA, Akehiko HOSHIDE, Kunihiro YOSHIMURA
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 37:133-143
The purpose of this study is to develop a void fraction correlation based on the void data measured by an X-ray CT scanner. The tests were carried out in an out-of-pile test facility that can simulate the high pressure and high temperature conditions
Autor:
Akira INOUE, Tatsuo KUROSU, Toshimasa AOKI, Masanobu FUTAGUCHI, Makoto YAGI, Shinichi MOROOKA, Akehiko HOSHIDE, Takao ISHIZUKA, Kunihiro YOSHIMURA, Hiroyuki YOSHIDA, Toru MITUTAKE, Nobuaki ABE, Akira KOZIMA, Tuyoshi NAKAJIMA, Satoshi NAKAMURA, Toshimi SAWA
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 37:710-720
Steam void fraction measurement test in a BWR fuel assembly has been carried out to prove the current BWR void prediction method. This report describes the experimental apparatus, experimental data, and evaluation results. The test was carried out in
Autor:
Masao Oishi, Akehiko Hoshide, Jun Hamada, Haruo Terasaka, Akira Inoue, Takao Morooka, Mamoru Akiyama, Kunihiro Yoshimura, Shinichi Ishizuka, Tatsuo Kagawa, Toru Mitsutake, Akira Kojima, Toshimasa Aoki, Yuichiro Yoshimoto
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 31:280-295
Nuclear Power Engineering Test Center (NUPEC) completed critical power test by simulated full scale assemblies to prove thermal-hydraulic design base reliability of BWR fuel assembly. This report describes experimental apparatus, experimental data an
Autor:
Mamoru Akiyama, Akira Inoue, Masao Ohishi, Akehiko Hoshide, Shinichi Morooka, Kunihiro Yoshimura, Takao Ishizuka
Publikováno v:
Nuclear Engineering and Design. 117:341-347
Post-BT heat transfer experiments on a full scale BWR ( 8 × 8 ) rod bundle were conducted at the Nuclear Power Engineering Test Center (NUPEC), which is sponsored by the Ministry of International Trade and Industry (MITI). Demineralized water was us
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