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. Furthermore, 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.
- Authors:
-
[2];
- Univ. of Tennessee, Knoxville, TN (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Stony Brook Univ., NY (United States)
- Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1606816
- Alternate Identifier(s):
- OSTI ID: 1573878
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Engineering and Design
- Additional Journal Information:
- Journal Volume: 357; Journal Issue: C; Journal ID: ISSN 0029-5493
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AGR; TRISO; BISON; radionuclide; release; diffusion
Citation Formats
Schappel, Danny, Terrani, Kurt, Snead, Lance L., and Wirth, Brian D. Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests. United States: N. p., 2019.
Web. doi:10.1016/j.nucengdes.2019.110428.
Schappel, Danny, Terrani, Kurt, Snead, Lance L., & Wirth, Brian D. Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests. United States. https://doi.org/10.1016/j.nucengdes.2019.110428
Schappel, Danny, Terrani, Kurt, Snead, Lance L., and Wirth, Brian D. Mon .
"Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests". United States. https://doi.org/10.1016/j.nucengdes.2019.110428. https://www.osti.gov/servlets/purl/1606816.
@article{osti_1606816,
title = {Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests},
author = {Schappel, Danny and Terrani, Kurt and Snead, Lance L. and Wirth, Brian D.},
abstractNote = {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. Furthermore, 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.},
doi = {10.1016/j.nucengdes.2019.110428},
journal = {Nuclear Engineering and Design},
number = C,
volume = 357,
place = {United States},
year = {Mon Nov 11 00:00:00 EST 2019},
month = {Mon Nov 11 00:00:00 EST 2019}
}
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