Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident
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概要
- 論文の詳細を見る
In the Japan Sodium Cooled Fast Reactor (JSFR) design, elimination of severe power burst events in the Core Disruptive Accident (CDA) is intended as an effective measure to ensure retention of the core materials within the reactor vessel. The design strategy is to control the potential of excessive void reactivity insertion in the initiating phase by selecting appropriate design parameters such as maximum void reactivity on one hand, and to exclude core-wide molten-fuel-pool formation, which has been the main issue of CDA, by introducing an inner duct on the other hand. The effectiveness of these measures is evaluated based on existing experimental data and computer simulation with validated analytical tools. It is judged that the present JSFR design can exclude severe power burst events. Phenomenological consideration of general characteristics and preliminary evaluations for the long-term material relocation and cooling phases gave the perspective that in-vessel retention would be attained with appropriate design measures.
- 2011-04-01
著者
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SATO Ikken
Japan Atomic Energy Agency
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KOTAKE Shoji
Japan Atomic Energy Agency
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NAKAI Ryodai
Japan Atomic Energy Agency
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Kotake Shoji
Japan Atomic Power Company
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TOBITA Yoshiharu
Japan Atomic Energy Agency
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Kubo Shigenobu
Japan Atomic Power Company
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KONISHI Kensuke
Japan Atomic Energy Agency
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KAMIYAMA Kenji
Japan Atomic Energy Agency
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TOYOOKA Jun-ichi
Japan Atomic Energy Agency
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KOYAMA Kazuya
Mitsubishi FBR Systems, Inc.
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VASSILIEV Yuri
National Nuclear Center
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VURIM Alexander
National Nuclear Center
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ZUEV Vladimir
National Nuclear Center
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KOLODESHNIKOV Alexander
National Nuclear Center
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Koyama Kazuya
Mitsubishi Fbr Systems Inc.
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