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

D. Schappel; K. Terrani; L. L. Snead; B. D. Wirth

doi:10.1016/j.nucengdes.2019.110428

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

D. Schappel, K. Terrani, L. L. Snead, B. D. Wirth

Research output: Contribution to journal › Article › peer-review

9 Scopus citations

Abstract

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.

Original language	English
Article number	110428
Journal	Nuclear Engineering and Design
Volume	357
DOIs	https://doi.org/10.1016/j.nucengdes.2019.110428
State	Published - Feb 2020
Externally published	Yes

Funding

The authors acknowledge the BISON and MOOSE code developers for their technical support of this work. The high-performance computing facilities made available by Idaho National Laboratory are gratefully acknowledged. This research has been partially sponsored by the Advanced Fuels Campaign of the Fuel Cycle R&D program, Office of Nuclear Energy , US Department of Energy , under contract DE-AC05-00OR22725 with UT- Battelle , LLC. The authors acknowledge the BISON and MOOSE code developers for their technical support of this work. The high-performance computing facilities made available by Idaho National Laboratory are gratefully acknowledged. This research has been partially sponsored by the Advanced Fuels Campaign of the Fuel Cycle R&D program, Office of Nuclear Energy, US Department of Energy, under contract DE-AC05-00OR22725 with UT-Battelle, LLC.

Funders	Funder number
Advanced Fuels Campaign
US Department of Energy	DE-AC05-00OR22725
Office of Nuclear Energy
Idaho National Laboratory

Keywords

AGR
BISON
Diffusion
Radionuclide
Release
TRISO

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title = "Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests",

abstract = "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.",

keywords = "AGR, BISON, Diffusion, Radionuclide, Release, TRISO",

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AB - 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.

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

Abstract

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Keywords

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