UO2-(Zr0.8Ca0.2)O1.8面心立方固溶体微球制备工艺研究  

Research of UO-(ZrCa)O FCC Solid Solution Spheres Preparation

作　　者：龙弟均 曾诚 卢长先[1] 李佳[1] Long Dijun;Zeng Cheng;Lu Zhangxian;Li Jia(Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院反应堆燃料及材料重点实验室,成都610213

出　　处：《核动力工程》2021年第2期168-172,共5页Nuclear Power Engineering

摘　　要：为研制出耐辐照的新型单相陶瓷燃料,采用溶胶-凝胶法,通过复合溶胶配制、分散胶凝、洗涤、干燥煅烧与烧结过程,开展了UO2-(Zr0.8Ca0.2)O1.8燃料微球制备工艺研究,制备出铀摩尔分数含量分别为30mol%、50mol%、70mol%的UO2-(Zr0.8Ca0.2)O1.8燃料微球样品。在对工艺过程进行分析的基础上,通过实验确定了工艺参数。采用X射线衍射(XRD)对3种燃料微球样品进行分析,分析结果表明:铀摩尔分数含量分别为30mol%、50mol%、70mol%的UO2-(Zr0.8Ca0.2)O1.8燃料微球样品均为面心立方(FCC)固溶体结构。In order to develop the single-phase ceramic fuel with good radiation resistance,the UO2-(Zr0.8Ca0.2)O1.8 microspheres with different uranium contents (30mol%,50mol%,70mol%)were prepared by Inner-Sol-Gel technique.The technique is with five processes including sol preparation,casting and gelation,washing,drying,and sintering.The parameters of this technique were fixed on the basis of analysis and experiment.The UO2-(Zr0.8Ca0.2)O1.8 spheres were analyzed by XRD.The results show that UO2-(Zr0.8Ca0.2)O1.8 microspheres with different uranium contents(30mol%,50mol%,70mol%) were FCC solid solution.

关 键 词：溶胶-凝胶法 面心立方(FCC)固溶体 铀锆钙 

分 类 号：TL352.2[核科学技术—核技术及应用]