BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -

Yoshiaki Tsukuda; Hirohisa Kaneko; Nobuaki Abe; Riichiro Suzuki; Hiroshi Hayashi; Toru Mitsutake; Shinichi Morooka; Koujun Isaka; Miyuki Akiba; Yasuhiro Masuhara; Yuji Nishino

BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -

Yoshiaki Tsukuda, Hirohisa Kaneko, Nobuaki Abe, Riichiro Suzuki, Hiroshi Hayashi, Toru Mitsutake, Shinichi Morooka, Koujun Isaka, Miyuki Akiba, Yasuhiro Masuhara, Yuji Nishino

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Abstract

Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, post boiling transition (post-BT) tests by the use of full-scale test assemblies simulating 9×9 fuel were carried out to evaluate BWR fuel integrity. Two kinds of post-BT tests, the steady-state post-BT test and transient post-BT test were performed, and the test results were applied to development of new heat transfer and rewet correlations for the estimation of fuel rod surface temperature.

Original language	English
Title of host publication	International Conference on Nuclear Engineering, Proceedings, ICONE
Pages	943-955
Number of pages	13
Volume	3
Publication status	Published - 2002
Externally published	Yes
Event	10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA Duration: 2002 Apr 14 → 2002 Apr 18

Other

Other	10th International Conference on Nuclear Engineering (ICONE 10)
City	Arlington, VA
Period	02/4/14 → 02/4/18

ASJC Scopus subject areas

Energy(all)
Engineering(all)

Cite this

Tsukuda, Y., Kaneko, H., Abe, N., Suzuki, R., Hayashi, H., Mitsutake, T., Morooka, S., Isaka, K., Akiba, M., Masuhara, Y., & Nishino, Y. (2002). BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -. In International Conference on Nuclear Engineering, Proceedings, ICONE (Vol. 3, pp. 943-955)

BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -. / Tsukuda, Yoshiaki; Kaneko, Hirohisa; Abe, Nobuaki et al.

International Conference on Nuclear Engineering, Proceedings, ICONE. Vol. 3 2002. p. 943-955.

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Tsukuda, Y, Kaneko, H, Abe, N, Suzuki, R, Hayashi, H, Mitsutake, T, Morooka, S, Isaka, K, Akiba, M, Masuhara, Y & Nishino, Y 2002, BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -. in International Conference on Nuclear Engineering, Proceedings, ICONE. vol. 3, pp. 943-955, 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, 02/4/14.

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abstract = "Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, post boiling transition (post-BT) tests by the use of full-scale test assemblies simulating 9×9 fuel were carried out to evaluate BWR fuel integrity. Two kinds of post-BT tests, the steady-state post-BT test and transient post-BT test were performed, and the test results were applied to development of new heat transfer and rewet correlations for the estimation of fuel rod surface temperature.",

author = "Yoshiaki Tsukuda and Hirohisa Kaneko and Nobuaki Abe and Riichiro Suzuki and Hiroshi Hayashi and Toru Mitsutake and Shinichi Morooka and Koujun Isaka and Miyuki Akiba and Yasuhiro Masuhara and Yuji Nishino",

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AU - Tsukuda, Yoshiaki

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AU - Suzuki, Riichiro

AU - Hayashi, Hiroshi

AU - Mitsutake, Toru

AU - Morooka, Shinichi

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AB - Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8×8 and 9×9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, post boiling transition (post-BT) tests by the use of full-scale test assemblies simulating 9×9 fuel were carried out to evaluate BWR fuel integrity. Two kinds of post-BT tests, the steady-state post-BT test and transient post-BT test were performed, and the test results were applied to development of new heat transfer and rewet correlations for the estimation of fuel rod surface temperature.

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BWR 9×9 fuel assembly thermal-hydraulic tests (1) - New formula for post boiling transition heat transfer correlation and rewet correlation -

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