Phenomena, gaps, and issues for neutronics modeling and simulation of FHRs

Journal Article · 25 September 2018 · Annals of Nuclear Energy (Oxford)

DOI: https://doi.org/10.1016/j.anucene.2018.08.035 · OSTI ID:1482094

Rahnema, Farzad ^[1]; Diamond, David ^[2]; Serghiuta, Dumitru ^[3]; Burke, Paul ^[1]

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1. Georgia Inst. of Technology, Atlanta, GA (United States)
2. Brookhaven National Lab. (BNL), Upton, NY (United States)
3. Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

On the path to deployment of any reactor, modeling tool verification and validation is a key step. Fluoride-Salt-Cooled High Temperature Reactors (FHR) pose challenges to neutronics modeling and simulation tools due to several design features of the reactor type. This paper presents a categorized list of phenomena that pose challenges to FHR modeling using current neutronics tools. These phenomena are presented in four categories: Fundamental Cross Section Data, Material Composition, Computational Methodology, and General Depletion. Here, a short path forward for these phenomena is also presented. In addition, a discussion of the resulting gaps in current codes is presented.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); Nuclear Regulatory Commission/Non-NUREG; USDOE
• Grant/Contract Number: SC0012704
• OSTI ID: 1482094
• Alternate ID(s): OSTI ID: 1636406
• Report Number(s): BNL-209441-2018-JAAM
• Journal Information: Annals of Nuclear Energy (Oxford), Vol. 123, Issue C; ISSN 0306-4549
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English