MOX乏燃料衰变热计算方法研究  

The Study on MOX Spent Fuel Decay Heat Calculation Method

作　　者：黎辉[1] 夏春梅[1] 丁谦学[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《中国核电》2016年第2期113-116,共4页China Nuclear Power

摘　　要：目前,铀钚混合氧化物(MOX)燃料已成为一种可用于商业核电厂成熟再循环核燃料。经过燃耗过的燃料在正常停堆或事故后停堆时会产生大量的衰变余热,而乏燃料衰变热是事故分析、余热排出系统和乏燃料池冷却系统设计的重要输入参数之一。UOX乏燃料中裂变产物主要来自于U和Pu等可裂变核素的裂变,U贡献最大;MOX乏燃料裂变产物主要来自于U、Pu和Am等可裂变核素的裂变,Pu贡献最大。UOX乏燃料衰变热可使用ANS—5.1的方法进行计算,但ANS—5.1中的衰变热计算方法不完全适用于MOX燃料。MOX燃料是核燃料可持续发展的重要途径,因此必须研究采用新方法计算MOX乏燃料的衰变热。该文研究使用ANS—5.1计算MOX乏燃料裂变产物衰变热,再使用ORIGEN—S程序计算MOX乏燃料的重核衰变热贡献份额,综合得到MOX乏燃料的总衰变热。The MOX fuel becomes a mature recycled fuel for commercial LWR today. The spent fuel will release large d^ay heat after normal or abnormal reactor shutdown. The spent fuel decay heat is an important input of accident analysis and some systems design. The UOX fuel fissionable dements include uranium and plutonium, with uranium as the main contributor. The MOX fuel fissionable elements include uranium, plutonium and americium, with plutonium as the main contributor. ANS-5.1 is applicable to calculate the decay heat of the UOX spent fuel, but not for MOX spent fuel. Because the MOX fuel is a useful way to solve the fission fuel problem, the MOX spent fuel decay heat must be calculated by a new method. ANS- 5.1 is used to calculate the fission product decay heat of the MOX ~t fuel, and ORIGEN-S is used to calculate the decay heat fraction of the heavy nuclides, and then get the total decay heat of the MOX spent fuel.

关 键 词：MOX 乏燃料 衰变热 裂变产物 重核 

分 类 号：TL24[核科学技术—核燃料循环与材料]