强激光与粒子束2012，Vol.24Issue(12)：3001-3005,5.DOI:10.3788/HPLPB20122412.3001
300#研究堆首炉中央孔道中子通量密度计算
Neutron flux calculation for central channel in first cycle of SPRR-300
杨万奎 1曾和荣 1冷军 1刘耀光1
作者信息
- 1. 中国工程物理研究院核物理与化学研究所,四川绵阳621900
- 折叠
摘要
Abstract
The physical model of the 300 # swimming pool research reactor(SPRR-300) based on the Monte Carlo code MCNP has been verified. Sophisticated modeling is conducted. An effective multiplication factor value of 1. 002 29 is obtained, existing a relative error of 0. 229% compared with the critical value. Meanwhile, a problem comes out that the interrupt and con-tinue-run with parallel version of MCNP doesn't work. The problem is solved through trail and error process. A reasonable application of flux tally average over a cell and flux tally at a point is suggested, namely the former is prior to the latter to tally in big volume. Comparison between calculation results and experimental data shows that the thermal neutron flux has a deviation of 4. 6% at a power level of 3 MW. That is to say, the calculated value and the experimental value agree well with each other, and the neutron flux result is dependable.关键词
中子反应堆/临界计算/MCNP程序/并行计算/接续运行Key words
neutron reactor/ criticality calculation/ MCNP code/ parallel calculation/ continue-run分类
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杨万奎,曾和荣,冷军,刘耀光..300#研究堆首炉中央孔道中子通量密度计算[J].强激光与粒子束,2012,24(12):3001-3005,5.
