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Title: Cluster dynamics simulation of uranium self-diffusion during irradiation in UO 2

Abstract

While fission fragments pass through UO 2 nuclear fuel, a considerable concentration of Frenkel pair defects (i.e. vacancies and interstitials) are created. The steady-state concentration of these defects leads to enhanced uranium self-diffusion, one of several fundamental kinetic parameters that control key engineering properties such as creep and fission gas swelling in UO 2 nuclear fuel. A cluster dynamics method to track point defects and defect clusters has been implemented in the MARMOT phase-field code in order to predict as-measured out-of-pile and irradiation enhanced thermal diffusivity. Here, the calculated uranium self-diffusion coefficient compares well with non-irradiated fuel measurements, and shows similar trends to those observed in irradiated fuel, which is a good result given the complexities introduced by non-stoichiometric compositions.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1565864
Alternate Identifier(s):
OSTI ID: 1564496
Report Number(s):
LA-UR-19-20856
Journal ID: ISSN 0022-3115
Grant/Contract Number:  
89233218CNA000001
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 527; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Uranium self-diffusion; Cluster dynamics; DFT

Citation Formats

Matthews, Christopher, Perriot, Romain, Cooper, Michael W. D., Stanek, Christopher R., and Andersson, David A. Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2. United States: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.151787.
Matthews, Christopher, Perriot, Romain, Cooper, Michael W. D., Stanek, Christopher R., & Andersson, David A. Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2. United States. doi:10.1016/j.jnucmat.2019.151787.
Matthews, Christopher, Perriot, Romain, Cooper, Michael W. D., Stanek, Christopher R., and Andersson, David A. Fri . "Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2". United States. doi:10.1016/j.jnucmat.2019.151787.
@article{osti_1565864,
title = {Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2},
author = {Matthews, Christopher and Perriot, Romain and Cooper, Michael W. D. and Stanek, Christopher R. and Andersson, David A.},
abstractNote = {While fission fragments pass through UO2 nuclear fuel, a considerable concentration of Frenkel pair defects (i.e. vacancies and interstitials) are created. The steady-state concentration of these defects leads to enhanced uranium self-diffusion, one of several fundamental kinetic parameters that control key engineering properties such as creep and fission gas swelling in UO2 nuclear fuel. A cluster dynamics method to track point defects and defect clusters has been implemented in the MARMOT phase-field code in order to predict as-measured out-of-pile and irradiation enhanced thermal diffusivity. Here, the calculated uranium self-diffusion coefficient compares well with non-irradiated fuel measurements, and shows similar trends to those observed in irradiated fuel, which is a good result given the complexities introduced by non-stoichiometric compositions.},
doi = {10.1016/j.jnucmat.2019.151787},
journal = {Journal of Nuclear Materials},
number = C,
volume = 527,
place = {United States},
year = {2019},
month = {9}
}

Journal Article:
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This content will become publicly available on September 6, 2020
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