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Title: Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel

Abstract

In this study, the effects of interaction layer (IL) on thermophysical properties of U-7Mo/Al dispersion fuel were examined. Microstructural analyses revealed that ILs were formed uniformly on U-Mo particles during heating of U-7Mo/Al samples. The IL volume fraction was measured by applying image analysis methods. The uranium loadings of the samples were calculated based on the measured meat densities at 298 K. The density of the IL was estimated by using the measured density and IL volume fraction. Thermal diffusivity and heat capacity of the samples after the heat treatment were measured as a function of temperature and volume fractions of U-Mo and IL. The thermal conductivity of IL-formed U-7Mo/Al was derived by using the measured thermal diffusivity, heat capacity, and density. The thermal conductivity obtained in the present study was lower than that predicted by the modified Hashin–Shtrikman model due to the theoretical model’s inability to consider the thermal resistance at interfaces between the meat constituents.

Authors:
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Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
National Research Foundation of Korea (NRF); USDOE National Nuclear Security Administration (NNSA) - Office of Defense Nuclear Nonproliferation - Office of Material Management and Minimization (NA-23) Reactor Conversion Program
OSTI Identifier:
1432373
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Journal Article
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 501; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
density; interaction layer; U-Mo/Al dispersion fuel; heat capacity; measured data; thermal conductivity; thermal diffusivity

Citation Formats

Cho, Tae Won, Kim, Yeon Soo, Park, Jong Man, Lee, Kyu Hong, Kim, Sunghwan, Lee, Chong Tak, Yang, Jae Ho, Oh, Jang Soo, and Sohn, Dong-Seong. Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel. United States: N. p., 2018. Web. doi:10.1016/j.jnucmat.2018.01.027.
Cho, Tae Won, Kim, Yeon Soo, Park, Jong Man, Lee, Kyu Hong, Kim, Sunghwan, Lee, Chong Tak, Yang, Jae Ho, Oh, Jang Soo, & Sohn, Dong-Seong. Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel. United States. doi:10.1016/j.jnucmat.2018.01.027.
Cho, Tae Won, Kim, Yeon Soo, Park, Jong Man, Lee, Kyu Hong, Kim, Sunghwan, Lee, Chong Tak, Yang, Jae Ho, Oh, Jang Soo, and Sohn, Dong-Seong. Sun . "Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel". United States. doi:10.1016/j.jnucmat.2018.01.027.
@article{osti_1432373,
title = {Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel},
author = {Cho, Tae Won and Kim, Yeon Soo and Park, Jong Man and Lee, Kyu Hong and Kim, Sunghwan and Lee, Chong Tak and Yang, Jae Ho and Oh, Jang Soo and Sohn, Dong-Seong},
abstractNote = {In this study, the effects of interaction layer (IL) on thermophysical properties of U-7Mo/Al dispersion fuel were examined. Microstructural analyses revealed that ILs were formed uniformly on U-Mo particles during heating of U-7Mo/Al samples. The IL volume fraction was measured by applying image analysis methods. The uranium loadings of the samples were calculated based on the measured meat densities at 298 K. The density of the IL was estimated by using the measured density and IL volume fraction. Thermal diffusivity and heat capacity of the samples after the heat treatment were measured as a function of temperature and volume fractions of U-Mo and IL. The thermal conductivity of IL-formed U-7Mo/Al was derived by using the measured thermal diffusivity, heat capacity, and density. The thermal conductivity obtained in the present study was lower than that predicted by the modified Hashin–Shtrikman model due to the theoretical model’s inability to consider the thermal resistance at interfaces between the meat constituents.},
doi = {10.1016/j.jnucmat.2018.01.027},
journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = C,
volume = 501,
place = {United States},
year = {2018},
month = {4}
}