MC simulation of thermal neutron flux of large samples irradiated by 14 MeV neutrons  

作　　者：BAI Yunfei WANG Dezhong MAUERHOFER Eric KETTLER John 

机构地区：[1]School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 200240 Shanghai, China [2]Institute of Energy Research IEF-6： Safety Research and Reactor Technology, Forschungszentrum Jiilich GmbH, 52425 Jiilich, Germany

出　　处：《Nuclear Science and Techniques》2010年第1期11-15,共5页核技术（英文）

基　　金：Supported by National Natural Science Foundation of China (No. 10675084);the Forschungszentrum Jülich GmbH, Germany

摘　　要：The response of a 14 MeV neutron-based prompt gamma neutron activation analysis (PGNAA) system,i.e.the prompt gamma-rays count rate and the average thermal neutron flux,is studied with a large concrete sample and with a homogeneous large sample,which is made of polyethylene and metal with various concentrations of hydrogen and cadmium using the MCNP-5 (Monte Carlo N-Particle) code.The average thermal neutron flux is determined by the analysis of the prompt gamma-rays using the thermal neutron activation of hydrogen in the sample,and the thermal and fast neutron activation of carbon graphite irradiation chamber of the PGNAA-system.Our results demonstrated that the graphite irradiation chamber of the PGNAA-system fairly operates,and is useful to estimate the average thermal neutron flux of large samples with various compositions irradiated by 14 MeV neutrons.The response of a 14 MeV neutron-based prompt gamma neutron activation analysis （PGNAA） system, i.e the prompt gamma-rays count rate and the average thermal neutron flux, is studied with a large concrete sample and with a homogeneous large sample, which is made of polyethylene and metal with various concentrations of hydrogen and cadmium using the MCNP-5 （Monte Carlo N-Particle） code. The average thermal neutron flux is determined by the analysis of the prompt gamma-rays using the thermal neutron activation of hydrogen in the sample, and the thermal and fast neutron activation of carbon graphite irradiation chamber of the PGNAA-system. Our results demonstrated that the graphite irradiation chamber of the PGNAA-system fairly operates, and is useful to estimate the average thermal neutron flux of large samples with various compositions irradiated by 14 MeV neutrons.

关 键 词：中子通量 中子辐照 大样本 MEV 中子活化分析 PGNAA 瞬发γ射线 模拟 

分 类 号：O212.1[理学—概率论与数理统计] TL375.4[理学—数学]