Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors
Imaizumi Y. Aoyagi M. Kamiyama K. Matsuba K.-I. Akaev A. Mikisha A. Baklanov V. Vurim A.
15 December 2023Elsevier Ltd
Annals of Nuclear Energy
2023#194
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.
Degraded core , In-place cooling , Severe accident , Sodium-cooled fast reactor
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Japan Atomic Energy Agency, Naritacho 4002, Ibaraki, Oarai, 311-1393, Japan
National Nuclear Center of the Republic of Kazakhstan, Beibyt atom St, Kurchatov, 071100, Kazakhstan
Japan Atomic Energy Agency
National Nuclear Center of the Republic of Kazakhstan
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