The simulation and analysis on the radiation fence of D-D neutron generator by Monte Carlo Method

Author

Yi Jie ; An Li-min ; Shi, Tao ; Liu Chun-xia ; Li Xiang-long

Author_Institution

Coll. of Phys. Sci. & Technol., Heilongjiang Univ., Harbin, China

Volume

2

fYear

2011

fDate

29-31 July 2011

Abstract

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 Proton´s 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.

Keywords

Monte Carlo methods; neutron sources; D-D neutron generator; MCNP procedure; Monte Carlo method; cement raw meal; fence material; neutron injection; optimum design; radiation fence; radiation protection analysis; radiation source shield; Analytical models; Detectors; Educational institutions; Lead; Neutrons; Photonics; Thickness measurement; MCNP simulation; The D-D neutron generator; fence material; radialization;

fLanguage

English

Publisher

ieee

Conference_Titel

Electronics and Optoelectronics (ICEOE), 2011 International Conference on

Conference_Location

Dalian

Print_ISBN

978-1-61284-275-2

Type

conf

DOI

10.1109/ICEOE.2011.6013211

Filename

6013211