The active commissioning process for a power reactor spent fuel reprocessing pilot plant in China  

作　　者：ZHANG TianXiang WANG Jian WU Tao CHEN GuangJun DI WU YongQing RU FaQuan 

机构地区：[1]The 404 Company Limited,China National Nuclear Corporation,Lanzhou 732850,China

出　　处：《Chinese Science Bulletin》2011年第23期2411-2415,共5页

摘　　要：The process of a power reactor spent fuel reprocessing pilot plant (hereinafter referred to as the "pilot plant") had been completed through active commissioning. Operational and technological parameters, such as shearing, dissolution, feed clarification, co-decontamination cycle, uranium and plutonium purification cycle, and the uranium and plutonium finishing facility, were identified. In addition, technical devices including extraction and mechanical equipment, electrical installation as well as instrumentation, and auxiliary systems for safety and adaptability were also verified. The commissioning results indicated that the recovery rate and decontamination coefficients of each system satisfied the designed index requirements and the qualified productions, i.e. uranium trioxide and plutonium dioxide, were produced. Monitored values at various monitoring points in the radiological protection system were within the control range and the discharge of waste water and waste gas complied with the relevant standards. This shows that independent and innovative technology for power reactor spent fuel reprocessing had been developed by our country.The process of a power reactor spent fuel reprocessing pilot plant (hereinafter referred to as the "pilot plant") had been completed through active commissioning. Operational and technological parameters, such as shearing, dissolution, feed clarification, co-decontamination cycle, uranium and plutonium purification cycle, and the uranium and plutonium finishing facility, were iden-tiffed. In addition, technical devices including extraction and mechanical equipment, electrical installation as well as instrumenta- tion, and auxiliary systems for safety and adaptability were also verified. The commissioning results indicated that the recovery rate and decontamination coefficients of each system satisfied the designed index requirements and the qualified productions, i.e. uranium trioxide and plutonium dioxide, were produced. Monitored values at various monitoring points in the radiological protection system were within the control range and the discharge of waste water and waste gas complied with the relevant standards. This shows that independent and innovative technology for power reactor spent fuel reprocessing had been developed by our countlT.

关 键 词：调试过程 乏燃料 动力堆 中国 试验 核燃料后处理 辅助系统 三氧化二砷 

分 类 号：TL941[核科学技术—辐射防护及环境保护]