高压釜的放射性废钠处理方案设计  

Design of Radioactive Sodium Waste Treatment Method Based on Autoclave

作　　者：王国芝[1] 石宁 李君瑜[1] Wang Guo-zhi;Shi Ning;Li Jun-yu

机构地区：[1]中国原子能科学研究院核工程设计研究所,北京102413

出　　处：《化工设计通讯》2023年第4期169-172,共4页Chemical Engineering Design Communications

摘　　要：在快堆的运行维护过程中,可能产生少量的放射性废钠。放射性废钠需要及时处理,否则可能产生燃烧或者爆炸的风险。国内尚无放射性废钠处理实践经验因此,对国外放射性废钠的处理方案进行调研和分析,经过比选确定使用水作为氧化剂,在封闭容器中分批次处理放射性废钠的方案是合理的。完成了基于高压釜的放射性废钠处理方案设计,并提出验证需求。During the operation and maintenance of fast reactors,a small amount of radioactive sodium waste may be produced.Radioactive sodium waste needs to be disposed of in time,otherwise there may be a risk of burning or explosion.There is no practical experience in the treatment of radioactive sodium waste in China.This paper investigates and analyzes foreign radioactive sodium waste treatment methods.After comparison,it is determined that it is reasonable to use water as an oxidant and treat radioactive sodium waste in batches in closed containers.The radioactive sodium waste treatment method based on autoclave is designed,and the verification requirements is proposed.

关 键 词：快堆 放射性废钠 废钠处理 

分 类 号：TL425[核科学技术—核技术及应用]