An Evaluation of the Thermophysical Properties of Stoichiometric CeO2 in Comparison to UO2 and PuO2

被引:67
作者
Nelson, Andrew T. [1 ]
Rittman, Dylan R. [1 ]
White, Joshua T. [1 ]
Dunwoody, John T. [1 ]
Kato, Masato [2 ]
McClellan, Kenneth J. [1 ]
机构
[1] Los Alamos Natl Lab, Los Alamos, NM 87545 USA
[2] Japan Atom Energy Agcy, Tokai, Ibaraki 3191194, Japan
关键词
INERT MATRIX FUEL; THERMAL-CONDUCTIVITY; ELECTRICAL-PROPERTIES; URANIUM-DIOXIDE; SOLID-SOLUTION; HEAT-CAPACITY; PHASE-DIAGRAM; PLUTONIUM; EXPANSION; CERIA;
D O I
10.1111/jace.13170
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The thermal conductivity of stoichiometric CeO2 was determined through measurement of thermal expansion from 313 to 1723 K, thermal diffusivity from 298 to 1473 K, and specific heat capacity from 313 to 1373 K. The thermal conductivity was then calculated as the product of the density, thermal diffusivity, and specific heat capacity. The thermal conductivity was found to obey an (A + BT)(-1) relationship with A = 6.776x10(-2) m center dot K center dot W-1 and B = 2.793 x 10(-4) m center dot W-1. Extrapolations of applied models were made to provide suggested data for the specific heat capacity, thermal diffusivity, and thermal conductivity data up to 1723 K. Results of thermal expansion and heat capacity measurements agreed well with the limited low-temperature data available in the literature. The thermal conductivity values provided in the current study are significantly higher than the only high-temperature data located for CeO2. This is attributed to the tendency of CeO2 to rapidly reduce at elevated temperatures given the available partial pressure of O-2 in air at ambient pressure. The CeO2 data are compared to literature values for UO2 and PuO2 to evaluate its suitability as a surrogate in nuclear fuel systems where thermal transport is a primary criterion for performance
引用
收藏
页码:3652 / 3659
页数:8
相关论文
共 49 条
[1]  
ANDREW J, 1976, TECH REP LA 6232 MS
[2]   ELECTRICAL CONDUCTIVITY OF URANIUM DIOXIDE [J].
BATES, JL ;
HINMAN, CA ;
KAWADA, T .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1967, 50 (12) :652-&
[3]   CHEMICAL THERMODYNAMIC REPRESENTATIONS OF [PUO2-X] AND [U1-ZPUZOW] [J].
BESMANN, TM ;
LINDEMER, TB .
JOURNAL OF NUCLEAR MATERIALS, 1985, 130 (FEB) :489-504
[4]  
BINGHAM P, 1993, MATER RES SOC S P, V1107, P421
[5]  
Chavan SV, 2004, J AM CERAM SOC, V87, P1977
[6]   Thermal diffusivity and conductivity of thorium-plutonium mixed oxides [J].
Cozzo, C. ;
Staicu, D. ;
Somers, J. ;
Fernandez, A. ;
Konings, R. J. M. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (1-2) :135-141
[7]   Inert matrix fuel strategies in the nuclear fuel cycle: the status of the initiative efforts at the 8th Inert Matrix Fuel Workshop [J].
Degueldre, C ;
Yamashita, T .
JOURNAL OF NUCLEAR MATERIALS, 2003, 319 :1-5
[8]   Concepts for an inert matrix fuel, an overview [J].
Degueldre, C ;
Paratte, JM .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) :1-6
[9]   STUDY OF THE FORMATION OF UO2-PUO2 SOLID-SOLUTION BY MEANS OF UO2-CEO2 SIMULATE [J].
DORR, W ;
HELLMANN, S ;
MAGES, G .
JOURNAL OF NUCLEAR MATERIALS, 1986, 140 (01) :7-10
[10]   ELECTRICAL-PROPERTIES OF CERIA-BASED OXIDES AND THEIR APPLICATION TO SOLID OXIDE FUEL-CELLS [J].
EGUCHI, K ;
SETOGUCHI, T ;
INOUE, T ;
ARAI, H .
SOLID STATE IONICS, 1992, 52 (1-3) :165-172