Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (1) project overview and progress until 2019

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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

2 Citations (Scopus)

Abstract

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 CDA 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 2019. Specific results in this paper are the validation of physical model describing B4C-SS eutectic reaction in the CDA analysis code, SIMMER-III, through the numerical analysis of the B4CSS eutectic melting experiments in which a B4C block was placed in a SS pool.

Original languageEnglish
Title of host publicationComputational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
Publication statusPublished - 2021
Event2021 28th International Conference on Nuclear Engineering, ICONE 2021 - Virtual, Online
Duration: Aug 4 2021Aug 6 2021

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume3

Conference

Conference2021 28th International Conference on Nuclear Engineering, ICONE 2021
CityVirtual, Online
Period8/4/218/6/21

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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