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Journal of Nuclear Science and Technology Volume 20, 1983 - Issue 7
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Original Paper

Boiling Water Reactor Loss of Coolant Tests Single Failure Tests with ROSA-III

Kunihisa SODA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
,
Kanji TASAKA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
,
Nobuaki ABE Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
&
Masayoshi SHIBA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
Pages 537-558 | Received 02 Nov 1981, Published online: 15 Mar 2012

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Seihiro ITOYA, Hideo NAGASAKA, Kumiaki MORIYA & Satoshi MIURA. (1988) Overview of SAFER03 Assessment Studies. Journal of Nuclear Science and Technology 25:3, pages 295-311.
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Hiroshige KUMAMARU, Yasuo KOIZUMI, Yutaka KUKITA & Kanji TASAKA. (1987) Investigation of Effect of Pressure Control System on BWR LOCA Phenomena Using ROSA-III Test Facility. Journal of Nuclear Science and Technology 24:10, pages 844-858.
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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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Mitsuhiro Suzuki, Kanji Tasaka, Yoshinari Anoda, Hiroshige Kumamaru, Hideo Nakamura & Masayoshi Shiba. (1985) Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor. Nuclear Technology 70:2, pages 189-203.
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Michio MURASE & Masanori NAITOH. (1985) BWR LOSS of Coolant Integral Tests with Two Bundle Loop, (II) Effect of ECCS Activation Modes on Thermal-Hydraulic Characteristics. Journal of Nuclear Science and Technology 22:4, pages 301-312.
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Takashi IKEDA, Atsuo YAMANOUCHI & Masanori NAITOH. (1985) BWR Recirculation Line Break Simulation Tests at Two Bundle Loop. Journal of Nuclear Science and Technology 22:4, pages 249-268.
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Michio MURASE & Masanori NAITOH. (1985) BWR Loss of Coolant Integral Tests with Two Bundle Loop, (I) Thermal-Hydraulic Characteristics in Parallel Channels. Journal of Nuclear Science and Technology 22:3, pages 213-224.
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K. Tasaka, M. Suzuki, Y. Anoda, Y. Koizumi, T. Yonomoto, H. Kumamaru, H. Nakamura & M. Shiba. (1985) ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor. Nuclear Technology 68:1, pages 77-93.
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