首页 | 本学科首页   官方微博 | 高级检索  
     

MCNP程序在反应堆临界计算中的应用
引用本文:钟兆鹏,施工,胡永明. MCNP程序在反应堆临界计算中的应用[J]. 核动力工程, 2003, 24(1): 8-11
作者姓名:钟兆鹏  施工  胡永明
作者单位:清华大学工程物理系,北京,100084;清华大学核能技术设计研究院,北京,100084
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于Keff值,计算结果与参值吻合较好,表明MCNP程序能够用于反应堆的临界计算。

关 键 词:临界计算  MCNP程序  控制棒的价值
文章编号:0258-0926(2003)01-008-04

Application of MCNP in the Criticality Calculation for Reactors
ZHONG Zhao-peng,SHI Gong,HU Yong-ming. Application of MCNP in the Criticality Calculation for Reactors[J]. Nuclear Power Engineering, 2003, 24(1): 8-11
Authors:ZHONG Zhao-peng  SHI Gong  HU Yong-ming
Affiliation:ZHONG Zhao-peng1,SHI Gong1,HU Yong-ming2
Abstract: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. 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.
Keywords:Criticality calculation  MCNP code  Value of control rods  
本文献已被 CNKI 维普 万方数据 等数据库收录!
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号