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

• 作者: Cao Shiwei Chen Desheng Qin Zhi Tan Cunmin
• 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
• 年，卷（期）: 2016,（1）
• 页码范围: 69-70
• 页数: 2页
• 分类号: O4

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.