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Survey of prospective techniques for molten salt reactor feed monitoring.

Authors :
Skutnik, Steve E.
Sobel, Peter W.
Swinney, Mathew W.
Hogue, Karen K.
Arno, Maggie M.
Chirayath, Sunil S.
Source :
Annals of Nuclear Energy. Dec2024, Vol. 208, pN.PAG-N.PAG. 1p.
Publication Year :
2024

Abstract

1 1 Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https://www.energy.gov/doe-public-access-plan). Safeguards verification measurements of nuclear material content in fresh fuel salt for liquid-fueled molten salt reactors (MSRs) are likely to be required as part of nuclear material accountancy for International Atomic Energy Agency safeguards. This paper presents a comprehensive review and evaluation of 18 potential candidate techniques to quantify total uranium and 235 U for input accountancy measurements for liquid-fueled MSRs. As part of an overall screening and down-selection effort to identify the most promising techniques for further development for an MSR feed monitoring system, this paper defines eight figures of merit (FOMs): reasonably achievable measurement uncertainty, measurement time required, capital cost, burden upon the facility operator, maintenance intensity, technological maturity, human capital requirements for operation, and whether the technique introduces a path for potential material removal. Each candidate technique is then evaluated across these FOMs to identify the techniques with the highest potential for future development for fresh fuel accountancy measurements in MSRs. Our findings indicate that no single technique or combination thereof currently has the requisite technological maturity for immediate implementation in nuclear material accountancy at a liquid-fueled MSR facility. While several promising techniques are identified, there is a critical lack of experimental data for most systems in the context of molten salt applications. • We propose criteria to screen feed accountancy techniques in molten salt reactors. • We evaluated 18 candidate techniques to identify the most promising for development. • Presently, no technique is sufficiently mature for MSR feed accountancy measurements. • Critical gaps in measurement data of actinide-bearing molten salts must be addressed. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
03064549
Volume :
208
Database :
Academic Search Index
Journal :
Annals of Nuclear Energy
Publication Type :
Academic Journal
Accession number :
178810725
Full Text :
https://doi.org/10.1016/j.anucene.2024.110796