四川大学学报（自然科学版）2011，Vol.48Issue(3)：641-646,6.DOI:10.3969/j.issn.0490-6756.2011.03.029
用MCNPX计算ADS金属靶散裂中子产额及散裂源中子效率
A MCNPX Caculation of the spallation neutron yields from various metal targets and the neutron source efficiency in ADS
景桂芬 1时磊1
作者信息
- 1. 四川大学物理科学与技术学院,成都610064
- 折叠
摘要
Abstract
In order to analyze the effect of the proton energy on the number of neutrons produced per source proton and the neutron yield spectra and values of neutron leakage distributions per proton over the cylindrical metal target surface in Accelerator Driven System (ADS),MCNPX are used to calculate them under different proton beam energy,and the results are compared with the results of the international organization institutions.The number of neutrons produced per source proton of tungsten target is larger but the tally of neutron leakage is smaller than lead target.Combining the MCNPX with MCNP5,the efficiency of the spallation neutions relative to fission neutrons for a subcritical benchmark system was calculated.关键词
中子产额/中子能谱/中子泄漏谱/源中子效率/MCNPX/金属靶Key words
neutron yields/ neutron yield spectra/neutron leakage distributions spectra/ source neutron efficiency/ MCNPX/ metal target分类
能源科技引用本文复制引用
景桂芬,时磊..用MCNPX计算ADS金属靶散裂中子产额及散裂源中子效率[J].四川大学学报（自然科学版）,2011,48(3):641-646,6.
