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Title: Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis

Abstract

Engineering scale nuclear fuel performance simulations can benefit by utilizing high-fidelity models running at a lower length scale. Lower length-scale models provide a detailed view of the material behavior that is used to determine the average material response at the macroscale. These lower length-scale calculations may provide insight into material behavior where experimental data is sparse or nonexistent. This multiscale approach is especially useful in the nuclear field, since irradiation experiments are difficult and expensive to conduct. The lower length-scale models complement the experiments by influencing the types of experiments required and by reducing the total number of experiments needed. This multiscale modeling approach is a central motivation in the development of the BISON-MARMOT fuel performance codes at Idaho National Laboratory. These codes seek to provide more accurate and predictive solutions for nuclear fuel behavior. One critical aspect of multiscale modeling is the ability to extract the relevant information from the lower length-scale sim- ulations. One approach, the asymptotic expansion homogenization (AEH) technique, has proven to be an effective method for determining homogenized material parameters. The AEH technique prescribes a system of equations to solve at the microscale that are used to compute homogenized material constants for use at themore » engineering scale. In this work, we employ AEH to explore the effect of evolving microstructural thermal conductivity and elastic constants on nuclear fuel performance. We show that the AEH approach fits cleanly into the BISON and MARMOT codes and provides a natural, multidimensional homogenization capability.« less

Authors:
 [1];  [1];  [2];  [1];  [1];  [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Ruhr Univ., Bochum (Germany) Interdisciplinary Centre for Advanced Materials Simulation
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1177605
Report Number(s):
INL/JOU-14-32113
Journal ID: ISSN 0927-0256; TRN: US1500046
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Computational Materials Science; Journal Volume: 99
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; 97 MATHEMATICS AND COMPUTING; NUCLEAR FUELS; PERFORMANCE; ASYMPTOTIC SOLUTIONS; IDAHO NATIONAL LABORATORY; COMPUTERIZED SIMULATION; Homogenization Methods; THERMAL CONDUCTIVITY; Elasticity; IRRADIATION; MICROSTRUCTURE; B Codes; M Codes; ASYMPTOTIC EXPANSION HOMOGENIZATION; MULTISCALE; NUCLEAR FUEL PERFORMANCE MODELING

Citation Formats

Hales, J. D., Tonks, M. R., Chockalingam, K., Perez, D. M., Novascone, S. R., Spencer, B. W., and Williamson, R. L.. Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis. United States: N. p., 2015. Web. doi:10.1016/j.commatsci.2014.12.039.
Hales, J. D., Tonks, M. R., Chockalingam, K., Perez, D. M., Novascone, S. R., Spencer, B. W., & Williamson, R. L.. Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis. United States. doi:10.1016/j.commatsci.2014.12.039.
Hales, J. D., Tonks, M. R., Chockalingam, K., Perez, D. M., Novascone, S. R., Spencer, B. W., and Williamson, R. L.. Sun . "Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis". United States. doi:10.1016/j.commatsci.2014.12.039.
@article{osti_1177605,
title = {Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis},
author = {Hales, J. D. and Tonks, M. R. and Chockalingam, K. and Perez, D. M. and Novascone, S. R. and Spencer, B. W. and Williamson, R. L.},
abstractNote = {Engineering scale nuclear fuel performance simulations can benefit by utilizing high-fidelity models running at a lower length scale. Lower length-scale models provide a detailed view of the material behavior that is used to determine the average material response at the macroscale. These lower length-scale calculations may provide insight into material behavior where experimental data is sparse or nonexistent. This multiscale approach is especially useful in the nuclear field, since irradiation experiments are difficult and expensive to conduct. The lower length-scale models complement the experiments by influencing the types of experiments required and by reducing the total number of experiments needed. This multiscale modeling approach is a central motivation in the development of the BISON-MARMOT fuel performance codes at Idaho National Laboratory. These codes seek to provide more accurate and predictive solutions for nuclear fuel behavior. One critical aspect of multiscale modeling is the ability to extract the relevant information from the lower length-scale sim- ulations. One approach, the asymptotic expansion homogenization (AEH) technique, has proven to be an effective method for determining homogenized material parameters. The AEH technique prescribes a system of equations to solve at the microscale that are used to compute homogenized material constants for use at the engineering scale. In this work, we employ AEH to explore the effect of evolving microstructural thermal conductivity and elastic constants on nuclear fuel performance. We show that the AEH approach fits cleanly into the BISON and MARMOT codes and provides a natural, multidimensional homogenization capability.},
doi = {10.1016/j.commatsci.2014.12.039},
journal = {Computational Materials Science},
number = ,
volume = 99,
place = {United States},
year = {Sun Mar 01 00:00:00 EST 2015},
month = {Sun Mar 01 00:00:00 EST 2015}
}