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Title: The thermal conductivity of mixed fuel U xPu 1-xO 2: molecular dynamics simulations

Abstract

Mixed oxides (MOX), in the context of nuclear fuels, are a mixture of the oxides of heavy actinide elements such as uranium, plutonium and thorium. The interest in the UO 2-PuO 2 system arises from the fact that these oxides are used both in fast breeder reactors (FBRs) as well as in pressurized water reactors (PWRs). The thermal conductivity of UO 2 fuel is an important material property that affects fuel performance since it is the key parameter determining the temperature distribution in the fuel, thus governing, e.g., dimensional changes due to thermal expansion, fission gas release rates, etc. For this reason it is important to understand the thermal conductivity of MOX fuel and how it differs from UO 2. Here, molecular dynamics (MD) simulations are carried out to determine quantitatively, the effect of mixing on the thermal conductivity of U xPu 1-xO 2, as a function of PuO 2 concentrations, for a range of temperatures, 300 – 1500 K. The results will be used to develop enhanced continuum thermal conductivity models for MARMOT and BISON by INL. These models express the thermal conductivity as a function of microstructure state-variables, thus enabling thermal conductivity models with closer connection to themore » physical state of the fuel.« less

Authors:
 [1];  [1];  [1];  [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
OSTI Identifier:
1223768
Report Number(s):
LA-UR-15-28079
TRN: US1500439
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; MIXED OXIDE FUELS; URANIUM DIOXIDE; PLUTONIUM OXIDES; THERMAL CONDUCTIVITY; PWR TYPE REACTORS; MOLECULAR DYNAMICS METHOD; FBR TYPE REACTORS; COMPUTERIZED SIMULATIONS; MIXTURES; TEMPERATURE DISTRIBUTION; MICROSTRUCTURE; PERFORMANCE; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K

Citation Formats

Liu, Xiang-Yang, Cooper, Michael William Donald, Stanek, Christopher Richard, and Andersson, Anders David Ragnar. The thermal conductivity of mixed fuel UxPu1-xO2: molecular dynamics simulations. United States: N. p., 2015. Web. doi:10.2172/1223768.
Liu, Xiang-Yang, Cooper, Michael William Donald, Stanek, Christopher Richard, & Andersson, Anders David Ragnar. The thermal conductivity of mixed fuel UxPu1-xO2: molecular dynamics simulations. United States. doi:10.2172/1223768.
Liu, Xiang-Yang, Cooper, Michael William Donald, Stanek, Christopher Richard, and Andersson, Anders David Ragnar. Fri . "The thermal conductivity of mixed fuel UxPu1-xO2: molecular dynamics simulations". United States. doi:10.2172/1223768. https://www.osti.gov/servlets/purl/1223768.
@article{osti_1223768,
title = {The thermal conductivity of mixed fuel UxPu1-xO2: molecular dynamics simulations},
author = {Liu, Xiang-Yang and Cooper, Michael William Donald and Stanek, Christopher Richard and Andersson, Anders David Ragnar},
abstractNote = {Mixed oxides (MOX), in the context of nuclear fuels, are a mixture of the oxides of heavy actinide elements such as uranium, plutonium and thorium. The interest in the UO2-PuO2 system arises from the fact that these oxides are used both in fast breeder reactors (FBRs) as well as in pressurized water reactors (PWRs). The thermal conductivity of UO2 fuel is an important material property that affects fuel performance since it is the key parameter determining the temperature distribution in the fuel, thus governing, e.g., dimensional changes due to thermal expansion, fission gas release rates, etc. For this reason it is important to understand the thermal conductivity of MOX fuel and how it differs from UO2. Here, molecular dynamics (MD) simulations are carried out to determine quantitatively, the effect of mixing on the thermal conductivity of UxPu1-xO2, as a function of PuO2 concentrations, for a range of temperatures, 300 – 1500 K. The results will be used to develop enhanced continuum thermal conductivity models for MARMOT and BISON by INL. These models express the thermal conductivity as a function of microstructure state-variables, thus enabling thermal conductivity models with closer connection to the physical state of the fuel.},
doi = {10.2172/1223768},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2015},
month = {10}
}

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