Mechanistic materials modeling for nuclear fuel performance

Tonks, Michael R.; Andersson, David; Phillpot, Simon R.; Zhang, Yongfeng; Williamson, Richard; Stanek, Christopher R.; Uberuaga, Blas P.; Hayes, Steven L.

doi:10.1016/j.anucene.2017.03.005

Title: Mechanistic materials modeling for nuclear fuel performance

Journal Article · Wed Mar 15 00:00:00 EDT 2017 · Annals of Nuclear Energy (Oxford)

DOI: https://doi.org/10.1016/j.anucene.2017.03.005 · OSTI ID:1369201

Tonks, Michael R. ^[1]; Andersson, David ^[2]; Phillpot, Simon R. ^[3]; Zhang, Yongfeng ^[4]; Williamson, Richard ^[4]; Stanek, Christopher R. ^[2]; Uberuaga, Blas P. ^[2]; Hayes, Steven L. ^[4]

Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical and Nuclear Engineering
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Univ. of Florida, Gainesville, FL (United States). Dept. of Materials Science and Engineering
Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation

Fuel performance codes are critical tools for the design, certification, and safety analysis of nuclear reactors. However, their ability to predict fuel behavior under abnormal conditions is severely limited by their considerable reliance on empirical materials models correlated to burn-up (a measure of the number of fission events that have occurred, but not a unique measure of the history of the material). In this paper, we propose a different paradigm for fuel performance codes to employ mechanistic materials models that are based on the current state of the evolving microstructure rather than burn-up. In this approach, a series of state variables are stored at material points and define the current state of the microstructure. The evolution of these state variables is defined by mechanistic models that are functions of fuel conditions and other state variables. The material properties of the fuel and cladding are determined from microstructure/property relationships that are functions of the state variables and the current fuel conditions. Multiscale modeling and simulation is being used in conjunction with experimental data to inform the development of these models. Finally, this mechanistic, microstructure-based approach has the potential to provide a more predictive fuel performance capability, but will require a team of researchers to complete the required development and to validate the approach.

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Research Organization:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States); Pennsylvania State Univ., University Park, PA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Contributing Organization:: Univ. of Florida, Gainesville, FL (United States)

Grant/Contract Number:: AC52-06NA25396; AC07-05ID14517

OSTI ID:: 1369201

Report Number(s):: LA-UR--17-21472

Journal Information:: Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Vol. 105; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams Janney, Dawn E.; Hayes, Steven L.; Adkins, Cynthia A. Nuclear Technology, Vol. 205, Issue 11 https://doi.org/10.1080/00295450.2019.1578573	journal	May 2019
A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 2: Thermal and Mechanical Properties Janney, Dawn E.; Hayes, Steven L.; Adkins, Cynthia A. Nuclear Technology https://doi.org/10.1080/00295450.2019.1623617	journal	July 2019

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