Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors

被引:2
|
作者
Imaizumi, Yuya [1 ]
Aoyagi, Mitsuhiro [1 ]
Kamiyama, Kenji [1 ]
Matsuba, Ken-ichi [1 ]
Akaev, Assan [2 ]
Mikisha, Anatoly [2 ]
Baklanov, Viktor [2 ]
Vurim, Alexandr [2 ]
机构
[1] Japan Atom Energy Agcy, Naritacho 4002, Oarai, Ibaraki 3111393, Japan
[2] Natl Nucl Ctr Republ Kazakhstan, Beibyt Atom St, Kurchatov 071100, Kazakhstan
关键词
Sodium-cooled fast reactor; Severe accident; Degraded core; In-place cooling; SIMMER-III; SEVERE RECRITICALITY; SAFETY ANALYSIS; ELIMINATION;
D O I
10.1016/j.anucene.2023.110107
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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.
引用
收藏
页数:11
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