Void measurement of BWR fuel assembly

Akira Inoue, Tatsuo Kurosu, Toshimasa Aoki, Masanobu Futaguchi, Makoto Yagi, Akira Kozima, Shinichi Morooka, Akehiko Hoshide, Takao Ishizuka, Kunihiro Yoshimura, Hiroyuki Yoshida, Toru Mitutake, Nobuaki Abe, Tuyoshi Nakajima

研究成果: Article

6 引用 (Scopus)

抄録

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 an out-of-pile test facility that can simulate the high pressure and high temperature conditions of BWRs. Water was used as a coolant. The void distribution in a BWR fuel assembly under BWR operating conditions was measured for the first time by an X-ray CT scanner, using an electrically heated test assembly which simulated a BWR fuel assembly on a full scale. Void fraction under steady and unsteady conditions was measured by an X-ray CT scanner and an X-ray densitometer. In steady state void test, 476 data were obtained. These data were compared with the current BWR void prediction method. Unsteady void test data were evaluated with the unsteady analytical code. It has been proved from these evaluation results that the verification of the current BWR void prediction method and unsteady analytical code has been accomplished.

元の言語English
ページ(範囲)710-720
ページ数11
ジャーナルNippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan
37
発行部数8
DOI
出版物ステータスPublished - 1995
外部発表Yes

Fingerprint

Void fraction
X rays
Densitometers
Test facilities
Coolants
Piles
Steam
Water
Temperature

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

これを引用

Inoue, A., Kurosu, T., Aoki, T., Futaguchi, M., Yagi, M., Kozima, A., ... Nakajima, T. (1995). Void measurement of BWR fuel assembly. Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, 37(8), 710-720. https://doi.org/10.3327/jaesj.37.710

Void measurement of BWR fuel assembly. / Inoue, Akira; Kurosu, Tatsuo; Aoki, Toshimasa; Futaguchi, Masanobu; Yagi, Makoto; Kozima, Akira; Morooka, Shinichi; Hoshide, Akehiko; Ishizuka, Takao; Yoshimura, Kunihiro; Yoshida, Hiroyuki; Mitutake, Toru; Abe, Nobuaki; Nakajima, Tuyoshi.

:: Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, 巻 37, 番号 8, 1995, p. 710-720.

研究成果: Article

Inoue, A, Kurosu, T, Aoki, T, Futaguchi, M, Yagi, M, Kozima, A, Morooka, S, Hoshide, A, Ishizuka, T, Yoshimura, K, Yoshida, H, Mitutake, T, Abe, N & Nakajima, T 1995, 'Void measurement of BWR fuel assembly', Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, 巻. 37, 番号 8, pp. 710-720. https://doi.org/10.3327/jaesj.37.710
Inoue, Akira ; Kurosu, Tatsuo ; Aoki, Toshimasa ; Futaguchi, Masanobu ; Yagi, Makoto ; Kozima, Akira ; Morooka, Shinichi ; Hoshide, Akehiko ; Ishizuka, Takao ; Yoshimura, Kunihiro ; Yoshida, Hiroyuki ; Mitutake, Toru ; Abe, Nobuaki ; Nakajima, Tuyoshi. / Void measurement of BWR fuel assembly. :: Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan. 1995 ; 巻 37, 番号 8. pp. 710-720.
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AU - Kozima, Akira

AU - Morooka, Shinichi

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AU - Abe, Nobuaki

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AB - 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 an out-of-pile test facility that can simulate the high pressure and high temperature conditions of BWRs. Water was used as a coolant. The void distribution in a BWR fuel assembly under BWR operating conditions was measured for the first time by an X-ray CT scanner, using an electrically heated test assembly which simulated a BWR fuel assembly on a full scale. Void fraction under steady and unsteady conditions was measured by an X-ray CT scanner and an X-ray densitometer. In steady state void test, 476 data were obtained. These data were compared with the current BWR void prediction method. Unsteady void test data were evaluated with the unsteady analytical code. It has been proved from these evaluation results that the verification of the current BWR void prediction method and unsteady analytical code has been accomplished.

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KW - thermal-hydraulics

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