Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (4) Validation of a multi-phase model for eutectic reaction between stainless steel and boron carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano

研究成果: Chapter in Book/Report/Conference proceedingConference contribution

抄録

Investigation of the eutectic reaction in a core disruptive accident of sodium cooled reactor is of importance since reactor criticality will be affected by the change in reactivity after eutectic reaction. In our previous study, a two-dimensional fast reactor safety analysis code, SIMMER-III, was extended to include a physical model to simulate the eutectic reaction between stainless steel (SS) and B4C. Based on experimental knowledge on eutectic reaction, the growth of eutectic material was modeled according to a parabolic rate law. Heat and mass transfer behaviors among reactor materials including a eutectic composition in solid and liquid phases were also modeled considering both equilibrium and non-equilibrium processes in phase change. Physical properties of the eutectic composition were also formulated based on experimental measurements for 5 mass% B4C-SS composition. In this study, we extended the eutectic reaction model to SIMMER-IV, a three-dimensional counterpart of SIMMER-III. We performed validation analysis using SIMMER-III and SIMMER-IV with the developed model based on an experiment, where a B4C pellet was immersed into a molten SS pool. Boron concentration in the pool was measured at several time points and the boron concentration after solidification of the molten pool was compared with the experiment post analysis result. Simulation results of boron distribution are comparable to the experimental results.

本文言語英語
ホスト出版物のタイトルNuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
DOI
出版ステータス出版済み - 2020
イベント2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference - Virtual, Online
継続期間: 4 4 20204 5 2020

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
2

会議

会議2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
CityVirtual, Online
Period4/4/204/5/20

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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