轻水堆乏燃料和钍燃料在ACR-700利用的探索  

Investigation of Potential Utilization for Light Water Reactor Spent Fuel and Thorium Fuel in ACR-700

作　　者：邹春燕[1,2] 陈金根[2] 蔡翔舟[2] 蒋大真[2] 郭锐[1,2] 陈堃[2] 郭威[2] 马余刚[2] 胡碧涛[1] 

机构地区：[1]兰州大学核科学与技术学院,甘肃兰州730000 [2]中国科学院上海应用物理研究所,上海201800

出　　处：《原子能科学技术》2013年第6期1008-1012,共5页Atomic Energy Science and Technology

基　　金：中国科学院知识创新工程"前沿领域计划"资助项目;国家自然科学基金资助项目(10805067)

摘　　要：轻水堆乏燃料和钍燃料的利用是解决乏燃料后处理问题和核燃料短缺的有效途径之一。本工作以ACR-700标准燃料为参考,研究了4种不同混合比例的轻水堆乏燃料及钍燃料在ACR-700中的k∞和燃耗。研究结果表明,将裂变产物分离后,轻水堆乏燃料的重锕系核素在ACR-700中可作为一很好的燃料;只要加入足够的启动燃料,钍燃料也可作为很好的转换燃料,使反应堆内生成233 U的速率大于易裂变燃料的消耗速率,233 U的生成对反应堆运行后期维持临界起重要作用。The potential utilization of light water reactor（LWR） spent fuel and thorium fuel is a very efficient way for solving spent fuel processing and nuclear fuel shortage problems.Four different mixed fuel types with LWR spent fuel and Th fuel were researched in ACR-700 using SCALE5.1 code system.Compared with the ACR-700 standard fuel,the fuel cycle model 1 and 4 can reach higher burnup.According to the research on the lattice physics of ACR-700 fuel bundle,it is indicated that LWR spent fuel after separation of the fission products is a very prospective fuel in ACR-700 and 232Th can be a preferable fertile isotope if sufficient booster fuel is supplied.

关 键 词：轻水堆乏燃料 钍燃料 ACR-700 

分 类 号：TL249[核科学技术—核燃料循环与材料]