Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 1; Project overview and progress until 2020

Yamano, Hidemasa ; Takai, Toshihide ; Emura, Yuki; Fukuyama, Hiroyuki*; Higashi, Hideo*; Nishi, Tsuyoshi*; Ota, Hiromichi*; Morita, Koji*; Nakamura, Kinya*; Fukai, Hirofumi*; Furuya, Masahiro*; Hong, Z.*; Erkan, N.*; Pellegrini, M.*

This paper describes the project overview and progress of experimental and analytical studies conducted until 2020. Specific results in this paper are the measurement of the eutectic reaction rates and the validation of physical model describing the eutectic reaction in the analysis code through the numerical analysis of the B $_{4}$ C-SS eutectic reaction rate experiments in which a B $_{4}$ C pellet was placed in a SS crucible.

Language	:	English
Journal	:	Proceedings of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) (Internet)
Volume	:
Number	:
Pages	:	12 Pages
Publication Year/Month	:	2022/09
Meeting title	:	13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13)
Held date	:	2022/09
Location (city)	:	Taichung
Location (country)	:	Taiwan
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	ナトリウム冷却高速炉; 炉心損傷事故; B $_{4}$ C
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省資源エネルギー庁

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Registration No. : BB20211653
JAEA Abstracts No. : 50001131
Paper Submission No. : 25898

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