Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (1) Project overview and progress until 2018

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Tsuyoshi Nishi, Hiromichi Ohta, Hiroyuki Fukuyama, Hideo Higashi, Xiaoxing Liu, Koji Morita, Kinya Nakamura

研究成果: Conference contribution

抄録

One of the key issues in a core disruptive accident (CDA) evaluation in sodium-cooled fast reactors is eutectic reactions between boron carbide (B4C) and stainless steel (SS) as well as its relocation. Such behaviors have never been simulated in CDA numerical analyses in the past, therefore it is necessary to develop a physical model and incorporate the model into the CDA analysis code. This study focuses on B4C-SS eutectic melting experiments, thermophysical property measurement of the eutectic melt, and physical model development for the eutectic melting reaction. The eutectic experiments involve the visualization experiments, eutectic reaction rate experiments and material analyses. The thermophysical properties are measured in a range from solid to liquid state. The physical model is developed for a severe accident computer code based on the measured data of the eutectic reaction rate and the physical properties. This paper describes the project overview and progress of experimental and analytical studies conducted until 2018. Specific results in this paper are boron concentration distributions of solidified B4C-SS eutectic sample in the eutectic melting experiments, which would be used for the validation of the eutectic physical model implemented into the computer code.

本文言語English
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Published - 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: 2020 4 42020 4 5

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
2

Conference

Conference2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
CityVirtual, Online
Period20/4/420/4/5

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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