2023 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[1O01-04] SFR 1

Wed. Sep 6, 2023 10:00 AM - 11:05 AM Room O (School of Eng. Bildg. 2F 522)

Chair:Hidetoshi Karasawa(JAEA)

10:30 AM - 10:45 AM

[1O03] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(34) Ultra-high temperature thermal analysis of SUS316L containing 14, 17mass%B4C using blackbody radiation during melting and solidification

*Hideo Higashi1, Makoto Ohtsuka1, Masayoshi Adachi1, Hiroyuki Fukuyama1, Hidemasa Yamano2 (1. Tohoku Univ., 2. JAEA)

Keywords:Sodium-cooled fast reactor, Boron carbide, Stainless steel, Melting behavior, Thermal analysis

This study is a part of the research aimed at constructing a model to simulate the eutectic reaction behavior between control rod material (B4C) and reactor structural material (SS) in core disruptive accidents of sodium-cooled fast reactors. We report the results of the thermal analysis of SUS316L containing 14, 17 mass% B4C during melting and solidification using a blackbody radiation type ultra-high temperature thermal analysis method.

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