Journal of Jilin University Science Edition

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14 MeV Neutron Shielding Material Designed by MCNP Code

LAN Min1, ZHANG Jingjie2, CHENG Daowen1   

  1. 1. School of Basic Sciences, Changchun University of Technology, Changchun 130012, China;2. College of Physics, Jilin University, Changchun 130012, China
  • Received:2014-10-30 Online:2015-03-26 Published:2015-03-24
  • Contact: CHENG Daowen E-mail:chengdaowen@mail.ccut.edu.cn

Abstract:

If hydrogenrich material is used to shield the 14 MeV neutrons produced by D-T neutron generator whose neutron yield is 108 n/s, its thickness must be more than 76 cm to make the neutron radiation dose less than 0.025 mSv/h. In order to decrease the thickness, the bilayer material consisted of copper and boronpolyethylene was used as 14 MeV neutron shielding material. The result of the calculation shows that the minimum thickness of the bilayer
 material is 52 cm, in which the thicknesses of copper and boronpolyethylene are 37 cm and 15 cm and the content of boron is 1.00%.

Key words: D-T neutron generator, neutron shielding material, copper, boronpolyethylene

CLC Number: 

  • O571.53