Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles

Simon, Pierre-Clément A.; Ke, Jia-Hong; Jiang, Chao; Aagesen, Larry K.; Jiang, Wen

doi:10.1016/j.jnucmat.2024.155464

Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles

Journal Article · Mon Oct 21 00:00:00 EDT 2024 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2024.155464· OSTI ID:2476359

^[1]; ^[1]; Jiang, Chao ^[1]; ^[1]; Jiang, Wen ^[1]

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

Tristructural isotropic (TRISO) particles are under consideration for use in several proposed advanced nuclear reactor concepts. The silicon carbide (SiC) layer in TRISO acts as a barrier to prevent the release of the fission products. However, despite remarkable retention, silver (Ag) release has been observed from intact particles, which requires investigation since the Ag isotope (^110m Ag) has a long half-life. Previous work focused on developing a multiscale, mechanistic model for Ag diffusion accounting for temperature and microstructure effect and has been successfully validated. In this work, we expand the previous model to account for irradiation-enhanced Ag diffusivity in SiC and improve its accuracy over a wider grain size and temperature ranges relevant for advanced reactor conditions. A temperature, grain size, and flux dependent diffusivity is therefore derived using the mesoscale code MARMOT and implemented in the fuel performance code BISON. The irradiation-enhanced Ag diffusivity in SiC is compared against experimental data and validated using BISON against Ag release measurements from the Advanced Gas Reactor Fuel Development and Qualification Program (AGR-1 and AGR-2). Herein, we quantify the impact of SiC grain size, irradiation, and temperature on Ag release. In agreement with previous studies, we find accounting for SiC grain size improves agreement between BISON predictions and experimental observations for most cases. In conclusion, we also find that accounting for irradiation improves agreement for cases where Ag release was underestimated, but the impact was less significant than accounting for microstructure.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2476359

Alternate ID(s):: OSTI ID: 2475679

Report Number(s):: INL/JOU--23-75711-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 603; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles

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