2-32 Release and Gathering of Semi-volatile Fission Products(Mo,Te)in the UO2 Simulated Fuel  

作　　者：Tan Cunmin Chen Desheng Cao Shiwei Qin Zhi 

机构地区：[1]不详

出　　处：《IMP & HIRFL Annual Report》2016年第1期69-70,共2页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）

摘　　要：The volatilization technology,which is used for pulverizing uranium oxide ceramic pellets,decladding,and removal of most of volatile and semi-volatile fission elements from spend fuel,has been developing as main treatment process for ADS nuclear fuel cycle.In the oxidation/reduction steps(400℃to 600℃),most of the volatile nuclides such as Kr,Xe,C-14,H-3,can be removed.However,the higher temperature is needed to release semi-volatile fission products.

分 类 号：O4[理学—物理]