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Nuclear Technology Volume 98, 1992 - Issue 1
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Technical Paper

Improvement of Evaluation Method for Initiating-Phase Energetics Based on CABRI-1 In-Pile Experiments

Nobuyuki NonakaPower Reactor and Nuclear Fuel Development Corporation O-arai Engineering Center, Fast Breeder Reactor Safety Engineering Section Safety Engineering Division, 4002 Narita-machi, O-arai, Ibaraki, 311-13 Japan
&
Ikken SatoPower Reactor and Nuclear Fuel Development Corporation O-arai Engineering Center, Fast Breeder Reactor Safety Engineering Section Safety Engineering Division, 4002 Narita-machi, O-arai, Ibaraki, 311-13 Japan
Pages 54-69 | Published online: 13 May 2017

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Ken-ichi Kawada & Tohru Suzuki. (2021) Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor. Journal of Nuclear Science and Technology 58:3, pages 347-360.
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Shoji Kotake, Hidemasa Yamano & Yutaka Sagayama. (2012) Safety Design Approach for a Large-Scale Japan Sodium-Cooled Fast Reactor (JSFR). Fusion Science and Technology 61:1T, pages 137-143.
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Yuichi ONODA, Yoshitaka FUKANO, Ikken SATO, Christophe MARQUIE & Bertrand DUC. (2011) Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors. Journal of Nuclear Science and Technology 48:2, pages 188-204.
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Yoshitaka FUKANO, Yuichi ONODA & Ikken SATO. (2010) Fuel Pin Behavior up to Cladding Failure under Pulse-Type Transient Overpower in the CABRI-FAST and CABRI-RAFT Experiments. Journal of Nuclear Science and Technology 47:4, pages 396-410.
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Yoshitaka FUKANO, Yuichi ONODA, Ikken SATO & Jean CHARPENEL. (2009) Fuel Pin Behavior under Slow-Ramp-type Transient-Overpower Conditions in the CABRI-FAST Experiments. Journal of Nuclear Science and Technology 46:11, pages 1049-1058.
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Tomoko Ishizu, Hiroshi ENDO & Hisashi NINOKATA. (2009) On Void Reactivity Limitation for the Core Loaded with Mixed Nitride Fuels. Journal of Nuclear Science and Technology 46:10, pages 981-994.
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Ikken Sato, Francette Lemoine & Dankward Struwe. (2004) Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments. Nuclear Technology 145:1, pages 115-137.
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HansK. FAUSKE, Kazuya KOYAMA & Shigenobu KUBO. (2002) Assessment of the FBR Core Disruptive Accident (CDA): The Role and Application of General Behavior Principles (GBPs). Journal of Nuclear Science and Technology 39:6, pages 615-627.
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HansK. FAUSKE & Kazuya KOYAMA. (2002) Assessment of Fuel Coolant Interactions (FCIs) in the FBR Core Disruptive Accident (CDA). Journal of Nuclear Science and Technology 39:6, pages 608-614.
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