Validating the BISON fuel performance code to integral LWR experiments
Abstract
BISON is a modern finite element-based nuclear fuel performance code that has been under development at the Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 2D axisymmetric, or 3D geometries. Code validation is underway and is the subject of this study. A brief overview of BISON’s computational framework, governing equations, and general material and behavioral models is provided. BISON code and solution verification procedures are described, followed by a summary of the experimental data used to date for validation of Light Water Reactor (LWR) fuel. Validation comparisons focus on fuel centerline temperature, fission gas release, and rod diameter both before and following fuel-clad mechanical contact. Comparisons for 35 LWR rods are consolidated to provide an overall view of how the code is predicting physical behavior, with a few select validation cases discussed in greater detail. Our results demonstrate that 1) fuel centerline temperature comparisons through all phases of fuel life are very reasonable with deviations between predictions and experimental data within ±10% for early life through high burnup fuel and only slightly out of these bounds formore »
- Authors:
-
- Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation
- ANATECH Corporation, San Diego, CA (United States)
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1357498
- Alternate Identifier(s):
- OSTI ID: 1488994
- Report Number(s):
- INL/JOU-15-36919
Journal ID: ISSN 0029-5493; PII: S0029549316000789
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Engineering and Design
- Additional Journal Information:
- Journal Volume: 301; 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; 97 MATHEMATICS AND COMPUTING; BISON; validation; verification
Citation Formats
Williamson, R. L., Gamble, K. A., Perez, D. M., Novascone, S. R., Pastore, G., Gardner, R. J., Hales, J. D., Liu, W., and Mai, A. Validating the BISON fuel performance code to integral LWR experiments. United States: N. p., 2016.
Web. doi:10.1016/j.nucengdes.2016.02.020.
Williamson, R. L., Gamble, K. A., Perez, D. M., Novascone, S. R., Pastore, G., Gardner, R. J., Hales, J. D., Liu, W., & Mai, A. Validating the BISON fuel performance code to integral LWR experiments. United States. https://doi.org/10.1016/j.nucengdes.2016.02.020
Williamson, R. L., Gamble, K. A., Perez, D. M., Novascone, S. R., Pastore, G., Gardner, R. J., Hales, J. D., Liu, W., and Mai, A. Thu .
"Validating the BISON fuel performance code to integral LWR experiments". United States. https://doi.org/10.1016/j.nucengdes.2016.02.020. https://www.osti.gov/servlets/purl/1357498.
@article{osti_1357498,
title = {Validating the BISON fuel performance code to integral LWR experiments},
author = {Williamson, R. L. and Gamble, K. A. and Perez, D. M. and Novascone, S. R. and Pastore, G. and Gardner, R. J. and Hales, J. D. and Liu, W. and Mai, A.},
abstractNote = {BISON is a modern finite element-based nuclear fuel performance code that has been under development at the Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 2D axisymmetric, or 3D geometries. Code validation is underway and is the subject of this study. A brief overview of BISON’s computational framework, governing equations, and general material and behavioral models is provided. BISON code and solution verification procedures are described, followed by a summary of the experimental data used to date for validation of Light Water Reactor (LWR) fuel. Validation comparisons focus on fuel centerline temperature, fission gas release, and rod diameter both before and following fuel-clad mechanical contact. Comparisons for 35 LWR rods are consolidated to provide an overall view of how the code is predicting physical behavior, with a few select validation cases discussed in greater detail. Our results demonstrate that 1) fuel centerline temperature comparisons through all phases of fuel life are very reasonable with deviations between predictions and experimental data within ±10% for early life through high burnup fuel and only slightly out of these bounds for power ramp experiments, 2) accuracy in predicting fission gas release appears to be consistent with state-of-the-art modeling and with the involved uncertainties and 3) comparison of rod diameter results indicates a tendency to overpredict clad diameter reduction early in life, when clad creepdown dominates, and more significantly overpredict the diameter increase late in life, when fuel expansion controls the mechanical response. In the initial rod diameter comparisons they were unsatisfactory and have lead to consideration of additional separate effects experiments to better understand and predict clad and fuel mechanical behavior. Results from this study are being used to define priorities for ongoing code development and validation activities.},
doi = {10.1016/j.nucengdes.2016.02.020},
journal = {Nuclear Engineering and Design},
number = C,
volume = 301,
place = {United States},
year = {Thu Mar 24 00:00:00 EDT 2016},
month = {Thu Mar 24 00:00:00 EDT 2016}
}
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Works referenced in this record:
Uncertainty and sensitivity analysis of the nuclear fuel thermal behavior
journal, December 2012
- Bouloré, A.; Struzik, C.; Gaudier, F.
- Nuclear Engineering and Design, Vol. 253
MOOSE: A parallel computational framework for coupled systems of nonlinear equations
journal, October 2009
- Gaston, Derek; Newman, Chris; Hansen, Glen
- Nuclear Engineering and Design, Vol. 239, Issue 10
Multidimensional multiphysics simulation of TRISO particle fuel
journal, November 2013
- Hales, J. D.; Williamson, R. L.; Novascone, S. R.
- Journal of Nuclear Materials, Vol. 443, Issue 1-3
Verification of the BISON fuel performance code
journal, September 2014
- Hales, J. D.; Novascone, S. R.; Spencer, B. W.
- Annals of Nuclear Energy, Vol. 71
An algorithm for the matrix-free solution of quasistatic frictional contact problems
journal, March 1999
- Heinstein, Martin W.; Laursen, Tod A.
- International Journal for Numerical Methods in Engineering, Vol. 44, Issue 9
Jacobian-free Newton–Krylov methods: a survey of approaches and applications
journal, January 2004
- Knoll, D. A.; Keyes, D. E.
- Journal of Computational Physics, Vol. 193, Issue 2
The radial distribution of plutonium in high burnup UO2 fuels
journal, February 1994
- Lassmann, K.; O'Carroll, C.; van de Laar, J.
- Journal of Nuclear Materials, Vol. 208, Issue 3
Extension of the TRANSURANUS burnup model to heavy water reactor conditions
journal, June 1998
- Lassmann, K.; Walker, C. T.; van de Laar, J.
- Journal of Nuclear Materials, Vol. 255, Issue 2-3
The ‘Fuel Rod Analysis ToolBox’: A general program for preparing the input of a fuel rod performance code
journal, July 2015
- Lassmann, K.; Schubert, A.; van de Laar, J.
- Annals of Nuclear Energy, Vol. 81
The structure of fuel element codes
journal, April 1980
- Lassmann, K.
- Nuclear Engineering and Design, Vol. 57, Issue 1
Evaluation of coupling approaches for thermomechanical simulations
journal, December 2015
- Novascone, S. R.; Spencer, B. W.; Hales, J. D.
- Nuclear Engineering and Design, Vol. 295
Verification and validation benchmarks
journal, March 2008
- Oberkampf, William L.; Trucano, Timothy G.
- Nuclear Engineering and Design, Vol. 238, Issue 3
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis
journal, March 2013
- Pastore, Giovanni; Luzzi, Lelio; Di Marcello, Valentino
- Nuclear Engineering and Design, Vol. 256
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling
journal, January 2015
- Pastore, Giovanni; Swiler, L. P.; Hales, J. D.
- Journal of Nuclear Materials, Vol. 456
Multidimensional multiphysics simulation of nuclear fuel behavior
journal, April 2012
- Williamson, R. L.; Hales, J. D.; Novascone, S. R.
- Journal of Nuclear Materials, Vol. 423, Issue 1-3
Works referencing / citing this record:
Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code
journal, September 2016
- Williamson, R. L.; Capps, N. A.; Liu, W.
- JOM, Vol. 68, Issue 11