Progress in Fabrication of UC Ceramic Nuclear Fuels

• 作者: Qin Zhi Tian Wei
• 来源期刊: 中国科学院近代物理研究所和兰州重离子研究装置年报:英文版
• 学科: 物理学
• 关键词: CONDUCTIVITY dioxide OXIDES
• 年，卷（期）: 2018,（1）
• 页码范围: 56-56
• 页数: 1页
• 分类号: O57

摘要

Uranium dioxide nuclear fuel has been widely used in pressurized water reactors(PWR),because of its high melting point,isotropic expansion,excellent radiation behaviors and mechanical properties[1].However,it is easy to embrittlement and the thermal conductivity is quite low.Compared with traditional uranium oxides nuclear fuel,the uranium carbide has extremely high hardness and no phase transition occurs in wide temperature range[2].The thermal conductivity,density and uranium fraction of UC is 21.7 W/(m
K)(1237 K),13.63 g/cm3 and 95.2%respectively,which are much higher than that of UO2.Uranium carbide ceramic fuel has been considered as a potential candidate nuclear fuel for the next-generation fast-neutron reactors,especially for the Accelerator-Driven Systems(ADS).Based on the accelerator driven recycling used nuclear fuel,uranium carbide can recrystallize with plutonium(Pu)and minor actinides(MAs).Therefore uranium carbide is chosen as the fuel format in ADS.