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)

10:15 AM - 10:30 AM

[1O02] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(33) Corrosion behavior of B4C pellet immersed in molten stainless steel

*Toshihide Takai1, Yuki Emura, Hidemasa Yamano (1. JAEA)

Keywords:Sodium-cooled fast reactor, Core disruptive accident, Boron carbide, Stainless steel, Eutectic

Corrosion behavior of B4C pellet immersed in molten stainless steel was investigated in order to clarify eutectic reaction mechanism as basic data for a physical model development to simulate the eutectic melting reaction and relocation behavior of boron carbide as a control rod material and stainless steel during a core disruptive accident in an advanced sodium-cooled fast reactor. This paper describes the analysis results of the immersion tests.

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