skip to main content

DOE PAGESDOE PAGES

Title: Mechanistic materials modeling for nuclear fuel performance

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 teammore » of researchers to complete the required development and to validate the approach.« less
Authors:
 [1] ;  [2] ;  [3] ;  [4] ;  [4] ;  [2] ;  [2] ;  [4]
  1. Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical and Nuclear Engineering
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Univ. of Florida, Gainesville, FL (United States). Dept. of Materials Science and Engineering
  4. Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation
Publication Date:
Report Number(s):
LA-UR-17-21472
Journal ID: ISSN 0306-4549
Grant/Contract Number:
AC52-06NA25396; AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 105; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Research Org:
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 Org:
USDOE Office of Nuclear Energy (NE)
Contributing Orgs:
Univ. of Florida, Gainesville, FL (United States)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Fuel performance modeling; Multiscale modeling and simulation
OSTI Identifier:
1369201
Alternate Identifier(s):
OSTI ID: 1415338

Tonks, Michael R., Andersson, David, Phillpot, Simon R., Zhang, Yongfeng, Williamson, Richard, Stanek, Christopher R., Uberuaga, Blas P., and Hayes, Steven L.. Mechanistic materials modeling for nuclear fuel performance. United States: N. p., Web. doi:10.1016/j.anucene.2017.03.005.
Tonks, Michael R., Andersson, David, Phillpot, Simon R., Zhang, Yongfeng, Williamson, Richard, Stanek, Christopher R., Uberuaga, Blas P., & Hayes, Steven L.. Mechanistic materials modeling for nuclear fuel performance. United States. doi:10.1016/j.anucene.2017.03.005.
Tonks, Michael R., Andersson, David, Phillpot, Simon R., Zhang, Yongfeng, Williamson, Richard, Stanek, Christopher R., Uberuaga, Blas P., and Hayes, Steven L.. 2017. "Mechanistic materials modeling for nuclear fuel performance". United States. doi:10.1016/j.anucene.2017.03.005. https://www.osti.gov/servlets/purl/1369201.
@article{osti_1369201,
title = {Mechanistic materials modeling for nuclear fuel performance},
author = {Tonks, Michael R. and Andersson, David and Phillpot, Simon R. and Zhang, Yongfeng and Williamson, Richard and Stanek, Christopher R. and Uberuaga, Blas P. and Hayes, Steven L.},
abstractNote = {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.},
doi = {10.1016/j.anucene.2017.03.005},
journal = {Annals of Nuclear Energy (Oxford)},
number = ,
volume = 105,
place = {United States},
year = {2017},
month = {3}
}