Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility

Hirschhorn, Jacob A.; Jaradat, Mustafa K.; Sweet, Ryan T.; Demkowicz, Paul A.; Balestra, Paolo; Strydom, Gerhard

doi:10.1016/j.nucengdes.2024.113720

Development and demonstration of a BISON–Griffin modeling framework for the design of targeted TRISO transient experiments in the Transient Reactor Test Facility

Journal Article · Wed Nov 27 00:00:00 EST 2024 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2024.113720· OSTI ID:2479674

^[1]; Jaradat, Mustafa K. ^[1]; ^[1]; ^[1]; Balestra, Paolo ^[1]; Strydom, Gerhard ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Uranium oxycarbide (UCO)-bearing tri-structural isotropic (TRISO) particle fuels are expected to be used in numerous U.S. commercial reactor applications within the next decade. Here, in this work, we reviewed historical particle fuel transient experiments to identify gaps in TRISO fuel performance transient testing. A BISON–Griffin modeling framework was then developed to conduct preliminary TRISO transient analyses and begin to address these gaps. The framework was demonstrated using limiting-case transient conditions from a prototypic high-temperature gas-cooled reactor (HTGR). It was then applied to develop a matrix of experiments that could be performed in the Transient Reactor Test Facility (TREAT) to (1) evaluate UCO-fueled particle performance at moderate and high heat rates, (2) assess whether historical testing involving UO₂-fueled particles is applicable to modern UCO-fueled particles, (3) deconvolute the impacts of temperature and heat rate on particle transient response, and (4) collect the data needed for fuel performance model validation and/or further development.

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This content will become publicly available on Thu Nov 27 00:00:00 EST 2025

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2479674

Alternate ID(s):: OSTI ID: 2480397

Report Number(s):: INL/JOU-24-80504-Rev000

Journal Information:: Nuclear Engineering and Design, Vol. 431; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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