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

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

研究成果: Contribution to conferencePaper査読

3 被引用数 (Scopus)

抄録

Eutectic reactions between boron carbide (B4C) and stainless steel (SS) as well as its relocation are one of the key issues in a core disruptive accident (CDA) evaluation in sodium-cooled fast reactors. Since such behaviors have never been simulated in CDA numerical analyses, it is necessary to develop a physical model and incorporate the model into the CDA analysis code. This study is focusing 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 the 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 by 2017. Specific results in this paper is 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.

本文言語英語
ページ418-427
ページ数10
出版ステータス出版済み - 2020
イベント14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, 米国
継続期間: 9 22 20199 27 2019

会議

会議14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country米国
CitySeattle
Period9/22/199/27/19

All Science Journal Classification (ASJC) codes

  • Fuel Technology
  • Nuclear Energy and Engineering

フィンガープリント 「Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (1) project overview」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル