Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO 2 nuclear fuel

M. H.A. Piro, J. Banfield, K. T. Clarno, S. Simunovic, T. M. Besmann, B. J. Lewis, W. T. Thompson

Research output: Contribution to journalArticlepeer-review

52 Scopus citations

Abstract

Predictive capabilities for simulating irradiated nuclear fuel behavior are enhanced in the current work by coupling thermochemistry, isotopic evolution and heat transfer. Thermodynamic models that are incorporated into this framework not only predict the departure from stoichiometry of UO 2 , but also consider dissolved fission and activation products in the fluorite oxide phase, noble metal inclusions, secondary oxides including uranates, zirconates, molybdates and the gas phase. Thermochemical computations utilize the spatial and temporal evolution of the fission and activation product inventory in the pellet, which is typically neglected in nuclear fuel performance simulations. Isotopic computations encompass the depletion, decay and transmutation of more than 2000 isotopes that are calculated at every point in space and time. These computations take into consideration neutron flux depression and the increased production of fissile plutonium near the fuel pellet periphery (i.e., the so-called "rim effect"). Thermochemical and isotopic predictions are in very good agreement with reported experimental measurements of highly irradiated UO 2 fuel with an average burnup of 102 GW d t(U) -1 . Simulation results demonstrate that predictions are considerably enhanced when coupling thermochemical and isotopic computations in comparison to empirical correlations. Notice: This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

Original languageEnglish
Pages (from-to)240-251
Number of pages12
JournalJournal of Nuclear Materials
Volume441
Issue number1-3
DOIs
StatePublished - 2013

Funding

The development of the Advanced Multi-Physics ( amp ) nuclear fuel performance code was funded by the Fuels Integrated Performance and Safety Code (IPSC) element of the Nuclear Energy Advanced Modeling and Simulations (NEAMS) program of the U.S. Department of Energy Office of Nuclear Energy (DOE/NE), Advanced Modeling and Simulation Office (AMSO).

FundersFunder number
Advanced Modeling and Simulation Office
DOE/NE
Office of Nuclear Energy

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