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Title: Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling

Abstract

The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code and a recently implemented physics-based model for the coupled fission gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO2 single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information from the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior modeling with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, higher deviations may be expected for values aroundmore » 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes.« less

Authors:
 [1];  [2];  [1];  [1];  [1];  [1];  [3];  [4];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  3. Polytechnic Univ. of Milan (Italy)
  4. European Commission, Karlsruhe (Germany). Joint Research Centre
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1162205
Alternate Identifier(s):
OSTI ID: 1246443
Report Number(s):
INL/JOU-14-31175
Journal ID: ISSN 0022-3115; TRN: US1600461
Grant/Contract Number:
AC07-05ID14517
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 456; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Fission gas behavior; Fuel modeling; Nuclear fuel; Sensitivity analysis; Uncertainty

Citation Formats

Pastore, Giovanni, Swiler, L. P., Hales, Jason D., Novascone, Stephen R., Perez, Danielle M., Spencer, Benjamin W., Luzzi, Lelio, Uffelen, Paul Van, and Williamson, Richard L. Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling. United States: N. p., 2014. Web. doi:10.1016/j.jnucmat.2014.09.077.
Pastore, Giovanni, Swiler, L. P., Hales, Jason D., Novascone, Stephen R., Perez, Danielle M., Spencer, Benjamin W., Luzzi, Lelio, Uffelen, Paul Van, & Williamson, Richard L. Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling. United States. doi:10.1016/j.jnucmat.2014.09.077.
Pastore, Giovanni, Swiler, L. P., Hales, Jason D., Novascone, Stephen R., Perez, Danielle M., Spencer, Benjamin W., Luzzi, Lelio, Uffelen, Paul Van, and Williamson, Richard L. Sun . "Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling". United States. doi:10.1016/j.jnucmat.2014.09.077. https://www.osti.gov/servlets/purl/1162205.
@article{osti_1162205,
title = {Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling},
author = {Pastore, Giovanni and Swiler, L. P. and Hales, Jason D. and Novascone, Stephen R. and Perez, Danielle M. and Spencer, Benjamin W. and Luzzi, Lelio and Uffelen, Paul Van and Williamson, Richard L.},
abstractNote = {The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code and a recently implemented physics-based model for the coupled fission gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO2 single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information from the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior modeling with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, higher deviations may be expected for values around 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes.},
doi = {10.1016/j.jnucmat.2014.09.077},
journal = {Journal of Nuclear Materials},
number = ,
volume = 456,
place = {United States},
year = {Sun Oct 12 00:00:00 EDT 2014},
month = {Sun Oct 12 00:00:00 EDT 2014}
}

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