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Numerical simulation of sodium-water reaction phenomena under small leakage condition in a steam generator

蒸気発生器内ナトリウム-水反応に関する数値解析研究

須田 一則 ; 渡部 晃*; 大島 宏之

Suda, Kazunori; Watanabe, Akira*; Ohshima, Hiroyuki

ナトリウム冷却高速炉の蒸気発生器内で発生するナトリウム-水反応現象を研究することを目的として、数値計算コードを開発した。本報では、SWAT-1R試験体系を用いて検証解析を実施した。その結果、SERAPHIMコードは、最高温度及び高温の領域を予測可能であり、その結果起こり得る高温ラプチャーの評価可能であることを明らかにした。

The purpose of this paper is to study numerical simulation of sodium-water reaction (SWR) phenomena under small leakage condition in a steam generator of a sodium cooled fast reactor. In this study, a numerical simulation was carried out regarding an experimental result of sodium water reaction test rig (SWAT-1R) located at Japan Atomic Energy Agency (JAEA). In the simulation, void fraction that could not be measured in the experiment concerning hydrogen and water vapor, development of high temperature region, maximum temperature, and flow characteristics of sodium and reaction products were estimated. At the same time, simulated temperature distributions and leakage flow rate were compared with measured data in the experiment, and it was confirmed that SERAPHIM was able to predict the maximum temperature that is important to evaluate overheating rupture of adjoining hear transfer tubes.

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