Development of an evaluation method for in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors

ナトリウム冷却高速炉の重大事故における損傷炉心のインプレース冷却の評価手法の開発

今泉 悠也 ; 青柳 光裕 ; 神山 健司  ; 松場 賢一  ; Akaev, A.*; Mikisha, A.*; Baklanov, V.*; Vurim, A.*

Imaizumi, Yuya; Aoyagi, Mitsuhiro; Kamiyama, Kenji; Matsuba, Kenichi; Akaev, A.*; Mikisha, A.*; Baklanov, V.*; Vurim, A.*

The cooling of the residual degraded core materials, which is called "in-place cooling", is one of the important factors for the in-vessel retention (IVR). For the evaluation of the in-place cooling, behavior in a SFR core which is cooled down by the sodium inflow through CRGT was simulated by a safety analysis code, SIMMER-III. As a result of the analysis, the core materials which were initially 2500 C were cooled down in several minutes. In order to analyze the in-place cooling, the method of phenomena identification and ranking table (PIRT) was applied, and several factors of thermal-hydraulic dynamics were extracted. An out-of-pile experiment which focuses on the extracted factors was conducted, and continuous oscillation of sodium level was observed in the experiment. Analysis by SIMMER-III for the experiment was conducted, and agreement between the experiment and the analysis result will be improved by development of an analysis model about gas motion.