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Nuclear Technology Volume 68, 1985 - Issue 1
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Technical Paper

ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor

K. TasakaJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
M. SuzukiJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
Y. AnodaJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
Y. KoizumiJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
T. YonomotoJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
H. KumamaruJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
,
H. NakamuraJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
&
M. ShibaJapan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
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Pages 77-93 | Published online: 12 May 2017

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Hideo NAKAMURA, Yutaka KUKITA & Kanji TASAKA. (1988) BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection. Journal of Nuclear Science and Technology 25:2, pages 169-179.
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Yasuo KOIZUMI, Taisuke YONOMOTO & Kanji TASAKA. (1987) Effect of Heat Generation Difference among Fuel Bundles on Core Thermal-Hydraulics during 200% and 5% Loss-of-Coolant Accident Experiments at ROSA-III. Journal of Nuclear Science and Technology 24:1, pages 61-74.
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Yasuo KOIZUMI & Kanji TASAKA. (1986) Investigation of Break Location Effects on Thermal-Hydraulics during Intermediate Break Loss-of-Coolant Accident Experiments at ROSA-III. Journal of Nuclear Science and Technology 23:11, pages 1008-1019.
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K. Tasaka, Y. Koizumi, Y. Kukita, H. Nakamura, Y. Anoda, M. Iriko, H. Kumamaru & M. Suzuki. (1985) Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident. Nuclear Technology 71:3, pages 628-643.
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