skip to main content
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

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. 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:
 [1]; ORCiD logo [2];  [3];  [4]
  1. Univ. of Tennessee, Knoxville, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Stony Brook Univ., NY (United States)
  4. Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (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. https://doi.org/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 = {2019},
month = {11}
}