Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code

Williamson, R. L.; Capps, N. A.; Liu, W.; Rashid, Y. R.; Wirth, B. D.

doi:10.1007/s11837-016-2115-7

Title: Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code

Journal Article · Tue Sep 27 00:00:00 EDT 2016 · JOM. Journal of the Minerals, Metals & Materials Society

DOI:https://doi.org/10.1007/s11837-016-2115-7· OSTI ID:1378340

^[1]; Capps, N. A. ^[2]; Liu, W. ^[3]; Rashid, Y. R. ^[3]; Wirth, B. D. ^[2]

Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of Tennessee, Knoxville, TN (United States)
ANATECH, San Diego, CA (United States)

Nuclear fuel operates in an extreme environment that induces complex multiphysics phenomena occurring over distances ranging from inter-atomic spacing to meters, and times scales ranging from microseconds to years. To simulate this behavior requires a wide variety of material models that are often complex and nonlinear. The recently developed BISON code represents a powerful fuel performance simulation tool based on its material and physical behavior capabilities, finite-element versatility of spatial representation, and use of parallel computing. The code can operate in full three dimensional (3D) mode, as well as in reduced two dimensional (2D) modes, e.g., axisymmetric radial-axial (R-Z) or plane radial-circumferential (R-θ), to suit the application and to allow treatment of global and local effects. A BISON case study was used in this paper to illustrate analysis of Pellet Clad Mechanical Interaction failures from manufacturing defects using combined 2D and 3D analyses. The analysis involved commercial fuel rods and demonstrated successful computation of metrics of interest to fuel failures, including cladding peak hoop stress and strain energy density. Finally, in comparison with a failure threshold derived from power ramp tests, results corroborate industry analyses of the root cause of the pellet-clad interaction failures and illustrate the importance of modeling 3D local effects around fuel pellet defects, which can produce complex effects including cold spots in the cladding, stress concentrations, and hot spots in the fuel that can lead to enhanced cladding degradation such as hydriding, oxidation, CRUD formation, and stress corrosion cracking.

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Research Organization:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Reactor Fleet and Advanced Reactor Development. Nuclear Reactor Technologies

Grant/Contract Number:: AC07-05ID14517; AC05-00OR22725

OSTI ID:: 1378340

Report Number(s):: INL/JOU-16-39006; PII: 2115

Journal Information:: JOM. Journal of the Minerals, Metals & Materials Society, Vol. 68, Issue 11; ISSN 1047-4838

Publisher:: SpringerCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 11 works

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References (12)

Multiscale development of a fission gas thermal conductivity model: Coupling atomic, meso and continuum level simulations Tonks, Michael R.; Millett, Paul C.; Nerikar, Pankaj Journal of Nuclear Materials, Vol. 440, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.008	journal	September 2013
Development of a multiscale thermal conductivity model for fission gas in UO2 Tonks, Michael R.; Liu, Xiang-Yang; Andersson, David Journal of Nuclear Materials, Vol. 469 https://doi.org/10.1016/j.jnucmat.2015.11.042	journal	February 2016
Multidimensional multiphysics simulation of nuclear fuel behavior Williamson, R. L.; Hales, J. D.; Novascone, S. R. Journal of Nuclear Materials, Vol. 423, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.012	journal	April 2012
Jacobian-free Newton–Krylov methods: a survey of approaches and applications Knoll, D. A.; Keyes, D. E. Journal of Computational Physics, Vol. 193, Issue 2 https://doi.org/10.1016/j.jcp.2003.08.010	journal	January 2004
Validating the BISON fuel performance code to integral LWR experiments Williamson, R. L.; Gamble, K. A.; Perez, D. M. Nuclear Engineering and Design, Vol. 301 https://doi.org/10.1016/j.nucengdes.2016.02.020	journal	May 2016
Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in <mml:math altimg="si236.gif" overflow="scroll" xmlns:xocs="http://www.elsevier.com/xml/xocs/dtd" xmlns:xs="http://www.w3.org/2001/XMLSchema" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns="http://www.elsevier.com/xml/ja/dtd" xmlns:ja="http://www.elsevier.com/xml/ja/dtd" xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:tb="http://www.elsevier.com/xml/common/table/dtd" xmlns:sb="http://www.elsevier.com/xml/common/struct-bib/dtd" xmlns:ce="http://www.elsevier.com/xml/common/dtd" xmlns:xlink="http://www.w3.org/1999/xlink" xmlns:cals="http://www.elsevier.com/xml/common/cals/dtd" xmlns:sa="http://www.elsevier.com/xml/common/struct-aff/dtd"><mml:mrow><mml:msub><mml:mrow><mml:mi mathvariant="normal">UO</mml:mi></mml:mrow><mml:mrow><mml:mn>2</mml:mn><mml:mo>±</mml:mo><mml:mi>x</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math>: Implications for nuclear fuel performance modeling Andersson, D. A.; Garcia, P.; Liu, X. -Y. Journal of Nuclear Materials, Vol. 451, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.03.041	journal	August 2014
Multidimensional simulations of hydrides during fuel rod lifecycle Stafford, D. S. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.06.037	journal	November 2015
Evaluation of missing pellet surface geometry on cladding stress distribution and magnitude Capps, Nathan; Montgomery, Robert; Sunderland, Dion Nuclear Engineering and Design, Vol. 305 https://doi.org/10.1016/j.nucengdes.2016.04.039	journal	August 2016
Multidimensional multiphysics simulation of TRISO particle fuel Hales, J. D.; Williamson, R. L.; Novascone, S. R. Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.070	journal	November 2013
MOOSE: A parallel computational framework for coupled systems of nonlinear equations Gaston, Derek; Newman, Chris; Hansen, Glen Nuclear Engineering and Design, Vol. 239, Issue 10 https://doi.org/10.1016/j.nucengdes.2009.05.021	journal	October 2009
Verification of the BISON fuel performance code Hales, J. D.; Novascone, S. R.; Spencer, B. W. Annals of Nuclear Energy, Vol. 71 https://doi.org/10.1016/j.anucene.2014.03.027	journal	September 2014
Formulation of the Constituent Distribution Model Implemented into the BISON Framework for the Analysis of Performance of Metallic Fuels with Some Initial Simulations Results Carlson, Neil; Unal, Cetin; Galloway, Jack https://doi.org/10.2172/1091811	report	August 2013

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