摘要
本文通过合理有效的近似,根据单群中子模型,建立了高通量工程试验堆(HFETR)堆芯反应性消耗率估算模型,探讨了影响反应性消耗率的因素,把估算模型和数值计算及堆的实际运行结果做了比较,得出了具有一般性的结论,并用堆物理理论解释了这一结论.本文还探讨了结论在研究堆和核电站堆芯装载设计中的应用.
Used some effective approximations tinder one group neutron model, a estimating modelof core reactivity consumption rate for HFETR has been presented in this paper. The factorsthat influence reactivity consumption rate have been discussed, the results come from the model, numical calculation and operating of HFETR have been compared, some general conclusions have given, and the conclusions have been explained by the reactor physics theory. Theconclusion's application in core loading design of test reactor and nuclear power reactor havebeen discussed.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1994年第5期418-423,共6页
Nuclear Power Engineering
关键词
HFETR
反应性消耗率
试验堆
堆芯
HFETR One group neutron model Reactivity consumption rate