摘要
用三维的蒙特卡罗程序(MCNP)进行临界计算。着重介绍堆芯和反射层的建模,利用MCNP程序的重复结构功能简化对堆芯的描述。以JRR3为例计算了几个不同棒位下keff值,计算结果与参考值吻合较好,表明MCNP程序能够用于反应堆的临界计算。
The criticality calculation is carried out with 3-D Monte Carlo code (MCNP). The paper focuses on the introduction of modelling of the core and reflector. The core description is simplified by using repetition structure function of MCNP. The coefficients, keff, in different control rods positions are calculated for the case of JRR3, and the result is consistent with that of the reference. This work shows that MCNP is applicable for reactor criticality calculation.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2003年第1期8-11,共4页
Nuclear Power Engineering
关键词
临界计算
MCNP程序
控制棒
价值
Control rods
Criticality (nuclear fission)
Monte Carlo methods
Numerical analysis
Three dimensional
