The Simulation and Analysis on the radiation fence of D-D neutron generator by Monte Carlo Method

摘要：

This paper simulates and analyses the irradiation fence around D-D neutron generator by a method, which combines Monte Carlo and practical measurement. Setting up the model of MCNP(the analog Monte Carlo method for Neutron and Protons transport) and analyzing the results are introduced. The energy of neutron from neutron generator is 2.5 MeV. Water has been used as the material of neutron fence. We use the MCNP procedure to simulate them and find the relation between the thickness of the fence material and the quantity of neutron injection. We take the result as a basis for designing the rapied analyzer of cement raw meal using D-D neutron generator. The results approve that Monte Carlo can be used in radiation protection analysis and optimum design of radiation source shield.

关键词： The D-D neutron generator radialization fence material MCNP simulation

作者: YI Jie AN Li-min Tao Shi LIU Chun-xia LI Xiang-long

作者单位: College of Physics Science and Technology, Heilongjiang University, Harbin 150080, China Institute of Radiation Technique,Northeast Normal University,ChangChun 130024, China

会议类型: 国际会议

会议名称: 2011 International Conference on Electronics and Optoelectronics(2011电子学与光电子学国际会议 ICEOE 2011)

会议地点: 大连

会议语种:英文

页码: 192-194

在线出版日期: 2011-07-29（万方平台首次上网日期，不代表论文的发表时间）