The MCNP Simulation Of D-D Neutron Generator Fence

Nuclear technique has been used in many fields including coal industry and theexploration of oil and gas. It has achieved remarkable economic and socialperformance. The neutron generator has many advantages, such as: low costs, highprecision,easycontrol,etc.Butitisdangerousforthebodytogettoomanyneutrons.This paper introduces the neutron, neutron source, and the principle of neutron fence.It also introduces MCNP (the analog Monte Carlo method for Neutron and Proton'stransport).SettingupthemodelofMCNPandanalyzingtheresultisbeenintroduce.The energy of neutron from neutron generator is 2.5 MeV. Water and polythenehas been used as material of neutron fence. We use the MCNP procedure to simulatethem and find the optimal thickness of the fence material. We take this as a basis fordesigning the rapied analyzer of cement raw meal using D-D neutron generator. Thefence material of the analyzer has manyadvantages, such as: smaller volume, smallermass, low costs, ease in handling, easy control, safety, etc. It doesn't influence themeasuredresult.