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今泉 悠也; 青柳 光裕; 神山 健司; 松場 賢一; Akaev, A.*; Mikisha, A.*; Baklanov, V.*; Vurim, A.*
Annals of Nuclear Energy, 194, p.110107_1 - 110107_11, 2023/12
被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)In severe accidents of SFRs, the cooling of the residual core materials, which is called "in-place cooling", is one of the important factors for In-Vessel Retention (IVR). For the evaluation, behavior of the in-place cooling was analyzed by the SIMMER-III code. In order to understand the in-place cooling, method of Phenomena Identification and Ranking Table (PIRT) was applied. Based on the result, an out-of-pile experiment which focused on the extracted factors was conducted. In the experiment, continuous oscillation of sodium level was observed by sodium vaporization and condensation. Analysis for the out-of-pile experiment was conducted by SIMMER-III, but the results were different between the experiment and the analysis. By investigation of the analysis result, it was revealed that the difference was due to occupation of non-condensable gas. Therefore, an analysis model of inter-cell gas mixing was newly developed, and the agreement was significantly improved by the new model.
加藤 慎也; 松場 賢一; 神山 健司; Akaev, A.*; Vurim, A.*; Baklanov, V.*
Proceedings of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) (Internet), 12 Pages, 2022/09
炉心崩壊事故(CDA)における溶融炉心物質の原子炉内保持(IVR)はナトリウム冷却高速炉の安全性を高めるために最も重要である。IVRを確保するための主要な課題の一つは、溶融炉心物質を炉心領域から効率的に排出するための制御棒案内管(CRGT)の設計である。CRGTの設計の有効性はCDA解析によって評価されるが、この解析には試験研究と連携した計算機コードの開発が合理的である。そこで、EAGLE-3プロジェクトと呼ばれる共同研究において、CRGTを介した溶融炉心物質の流出挙動を課題の一つとして試験研究が進められてきた。本試験研究で得られた知見はSIMMERコードの開発に反映される。このプロジェクトでは、CRGTを通じた溶融炉心物質の流出挙動を把握するために、溶融アルミナを燃料模擬物質とした一連の炉外試験が行われた。本研究では、CRGT内の内部構造物が溶融炉心物質の流出挙動に与える影響を調べるため、内部構造物を有するダクトを溶融アルミナが流下する炉外試験のデータを分析した。さらに、SIMMERコードによる試験後の解析を行い、試験結果との比較を行った。
松場 賢一; 加藤 慎也; 神山 健司; Akaev, A.*; Baklanov, V.*
no journal, ,
深さと容積が制限されたナトリウムプレナム領域を模擬したナトリウムプール中へ模擬溶融炉心物質(溶融アルミナ)を流出させる試験の結果に基づき、当該プレナム領域へ流出した溶融炉心物質の冷却性について検討し、溶融炉心物質が粒子状の固化物となって堆積する条件を明らかにした。
今泉 悠也; 青柳 光裕; 神山 健司; 松場 賢一; Akaev, A.*; Mikisha, A.*; Baklanov, V.*; Vurim, A.*
no journal, ,
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. Out-of-pile experiments which focus on the extracted factors were conducted, and continuous oscillations of sodium level were observed in the experiments. Analyses by SIMMER-III for the experiments were conducted, but the sodium level oscillation was not fully simulated in the analysis of IPCO-1. By investigation of the analysis result, it was revealed that the difference was due to partial occupation of non-condensable gas. In order to pre-vent the unrealistic occupation, the analysis model of inter-cell gas mixing was newly developed, and the agreement between experiment and analysis was significantly improved by that.
