Development of physical models to simulate disrupted core in metal-fuel sodium-cooled fast reactors

Tagami, Hirotaka*; Okano, Yasushi; Yamano, Hidemasa

The metal-fuel specific physical models for uranium-iron eutectic reaction and metal fuel pin behavior have been developed and incorporated into the SIMMER-III/IV code for safety analyses of metal-fuel sodium-cooled fast reactors. The TREAT M6 experimental analysis was performed to validate the metal-fuel pin model.

Language	:	English
Journal	:	Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet)
Volume	:
Number	:
Pages	:	12 Pages
Publication Year/Month	:	2025/08
Meeting title	:	21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21)
Held date	:	2025/08
Location (city)	:	Busan
Location (country)	:	Korea
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DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	sodium-cooled fast reactor; Metal Fuel; CDA; SIMMER; TREAT Reactor
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Cooperating Institute	:	経済産業省

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Registration No. : BB20241909
JAEA Abstracts No. : 54000174
Paper Submission No. : 30568

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