Thermal Conductivity of UO2-BeO-Gd2O3 Nuclear Fuel Pellets

被引:5
作者
Camarano, D. M. [1 ]
Mansur, F. A. [1 ]
Santos, A. M. M. [1 ]
Ribeiro, L. S. [1 ]
Santos, A. [1 ]
机构
[1] CDTN, Struct Integr & Nucl Mat Serv, BR-31270901 Belo Horizonte, MG, Brazil
关键词
Beryllium oxide; Gadolinium oxide; Laser flash method; Nuclear fuel pellets; Thermal conductivity; Thermal diffusivity; Thermal quadrupole method; Uranium dioxide; DIOXIDE;
D O I
10.1007/s10765-019-2574-5
中图分类号
O414.1 [热力学];
学科分类号
摘要
In the present paper, the influence of the beryllium oxide addition to increase the thermal conductivity in uranium dioxide fuel pellets containing gadolinium oxide as burnable poison was investigated. Fuel pellets of UO2, UO2-BeO-Gd2O3, and UO2-Gd2O3 were obtained in concentrations of 2-3 wt % of BeO and 6 wt % of Gd2O3. The thermal diffusivity was determined at room temperature and until 773 K by Laser Flash and Thermal Quadrupole methods, respectively. The thermal diffusivity and thermal conductivity were normalized to 95 % TD (theoretical density). The maximum relative expanded uncertainties of the thermal diffusivity and thermal conductivity measurements were estimated to be 7.5 % and 8.0 %, respectively. In addition, the obtained results were compared with the theoretical models and experimental data given in the literature. The results showed an increase in the thermal diffusivity and conductivity of the UO2 pellets with additions of BeO as compared to the values obtained with UO2 and UO2-Gd2O3 pellets.
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页数:9
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