不同燃料组合在液态氟盐冷却高温堆中的物理性能研究  

Physical-property study on liquid fluoride-salt-cooled high temperature reactor loaded with different kinds of fuel mixtures

作　　者：陈亮[1,2] 陈金根[2] 李晓晓[2] 蔡翔舟[2] 孙建友[1,2] 蒋大真[2] 姚泽恩[1] 

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

出　　处：《核技术》2014年第3期54-58,共5页Nuclear Techniques

基　　金：中国科学院战略性先导科技专项(No.XDA02010100)资助

摘　　要：液态氟盐冷却高温堆是第四代反应堆中的一种具有极大优势的堆型,对其燃料的研究工作具有重要的意义。本工作采用SCALE5.1程序包,对六种不同燃料组合在高温球床堆中的物理性能进行了研究,分别比较了剩余反应性、等效满功率运行天数、燃耗和中子能谱等重要参数。结果显示,采用233U或235U启堆时,使用232Th的实际转换成裂变材料的量不如使用238U转换的多,并会消耗更多的核燃料;采用239Pu启堆时,使用232Th可使反应堆维持较长的时间,而使用238U却导致反应堆很快不能自持。研究表明,从节约核燃料和延长堆芯寿期的角度看,在不进行在线换料后处理的情况下,232Th在热堆中的表现不如238U,但在超热堆中238U的表现不如232Th。Background： Liquid fluoride-salt-cooled high temperature reactor, one of the GEN-IV reactors, has great advantages comparatively, and the research on its fuel is of great significance. Purpose： The aim is to study the physical properties of high-temperature pebble-bed reactors loaded with six different fuel mixtures. Methods： We used SCALE5.1 package to compute some important parameters like excess reactivity, full power operation days, burnup and neutron spectrum. Results： The results show that the true conversions of 232Th are much less than those of 238U when mixed with 233U or 235U. With 239pu for starting, 232Th contributes to making the reactor running longer than that with 238U. Conclusion： With respect to saving fuel and extending the life of the core, without online refueling and reprocessing, 232Th is underperformed in thermal reactor compared with 238U, however, it is the opposite in epithermal neutron reactor.

关 键 词：高温堆 球床堆 Pebble球 TMSR(Thorium MOLTEN-SALT Reactor) 超热中子堆 

分 类 号：TL329[核科学技术—核技术及应用]