Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests

•BISON showed agreement with German data for Ag, Cs, and Sr release from TRISO fuel.•The recommended diffusion coefficients did not provide agreement AGR-1 fuel.•Refit the Ag, Cs, and Sr diffusion coefficients for better agreement with AGR-1 data. This article presents calculated radionuclide releas...

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Bibliographic Details
Published in:Nuclear engineering and design 2020-02, Vol.357 (C), p.110428, Article 110428
Main Authors: Schappel, D., Terrani, K., Snead, L.L., Wirth, B.D.
Format: Article
Language:English
Subjects:
Accuracy
AGR
Annealing
BISON
Compacts
Diffusion
Fission products
Fuels
Irradiation
Post-irradiation
Radioisotopes
Radionuclide
Release
Silicon carbide
TRISO
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Summary:•BISON showed agreement with German data for Ag, Cs, and Sr release from TRISO fuel.•The recommended diffusion coefficients did not provide agreement AGR-1 fuel.•Refit the Ag, Cs, and Sr diffusion coefficients for better agreement with AGR-1 data. This article presents calculated radionuclide release fractions from TRISO fuel during post-irradiation annealing and comparison with AGR-1 irradiated TRISO compacts using the BISON fuel performance code. The BISON code was found to produce good agreement in an analytical comparison and with legacy German TRISO compact irradiation data. However, the recommended IAEA fission product diffusion coefficients did not produce good agreement with the 2014 AGR-1 data (Demkowicz et al., 2015). Thus, the diffusion coefficients prefactors and activation energies were modified to obtain best agreement with the recent AGR data. Future work involves investigating the release behavior of silver from silicon carbide and implementing methods to provide predictive capability for the silver release behavior.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2019.110428