Establishment of Freezing Model for Reactor Safety Analysis

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概要

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• A mechanistic simulation of molten core-material relocation is required to reasonably assess consequences of postulated core disruptive accidents (CDAs) in fast reactors (FRs). The dynamics of molten core-material freezing when it is driven into the channels surrounding the core region plays an important role since this affects fuel removal from the core region. Therefore, a mechanistic model for freezing behavior was developed and introduced into the FR safety analysis code, SIMMER-III, in this study. Based on the micro-physics of crystallization, two key assumptions, supercooling of melt in the vicinity of the wall and melt-wall contact resistance due to imperfect contact, were introduced. As a result, encouraging agreement both with measured melt-penetration lengths and freezing modes of UO2 and metals was obtained. Furthermore, in order to reinforce the developed model, a semi-empirical correlation to predict the supercooling temperature was found. The developed model with the new correlation reproduced both stainless steel freezing and alumina freezing.

• 一般社団法人 日本原子力学会の論文
• 2006-10-25

著者

• TOBITA Yoshiharu

  Japan Atomic Energy Agency

• KAMIYAMA Kenji

  Japan Atomic Energy Agency

• BREAR David

  Japan Atomic Energy Agency

• KONDO Satoru

  Japan Atomic Energy Agency

関連論文

• Thermophysical Properties of Lead-Bismuth Eutectic Alloy in Reactor Safety Analyses
• Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident
• ICONE11-36388 RISK ANALYSIS OF THE AQUEOUS FAST REACTOR FUEL CYCLE FACILITY IN THE CONCEPTUAL DESIGN STAGE
• Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident
• Establishment of Freezing Model for Reactor Safety Analysis

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