A Preliminary validation study for removal performance of iodine gas in sodium pool with a simplified approach

Kam, D. H.*; Grabaskas, D.*; Starkus, T.*; Bucknor, M.*; Uchibori, Akihiro

Removal of gaseous radionuclides from the bubbles released into the sodium pool is an important consideration of fuel pin failure accident in sodium-cooled fast reactors. To support modeling of this phenomenon as a part of development of the SRT (Simplified Radionuclide Transport) code in Argonne National Laboratory, numerical analysis of experiment on Iodine gas transport to sodium pool was performed. A proposed evaluation method can be regarded to be reasonably predicting the measured decontamination factors.

Language	:	English
Journal	:	Transactions of the American Nuclear Society
Volume	:	126
Number	:	1
Pages	:	p.536 - 539
Publication Year/Month	:	2022/06
Meeting title	:	2022 American Nuclear Society Annual Meeting; Embedded Topical Meetings on Advances in Thermal Hydraulics (ATH 2022)
Held date	:	2022/06
Location (city)	:	Anaheim
Location (country)	:	U.S.A.
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.13182/T126-38052
DOI for research data	:
Keywords	:	ナトリウム冷却高速炉; ソースターム; 除染係数; 数値解析
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	Argonne National Laboratory

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Registration No. : BB20220048
JAEA Abstracts No. : 50000918
Paper Submission No. : 25636

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