基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计

doi:10.11889/j.0253-3219.2015.hjs.38.090604

Nuclear Techniques ›› 2015, Vol. 38 ›› Issue (9): 90604-090604.doi: 10.11889/j.0253-3219.2015.hjs.38.090604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source

HE Dan1,2 SONG Yingming2 ZOU Shuliang1 XU Shoulong1,2 WANG Xiaodong2 ZHU Zhichao2 TAN Zhengan2 HE Zhifeng1 WANG Xinlin3

1(Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities, Hengyang 421001, China) 2(School of Nuclear Science and Technology of University of South China, Hengyang 421001, China) 3(School of Electrical Engineering of University of South China, Hengyang 421001, China)

Received:2015-04-29 Revised:2015-07-05 Online:2015-09-10 Published:2015-09-10

Abstract

Abstract: Background: New material for the reactor shielding structure is one type of cast-steel impurity doping actinide elements have been adopted. The design parameters of the shielding performance testing device for the various parts of reactor can be obtained by Monte Carlo method. Purpose: This study aims to test the shielding performance of the shielding material of reactor. Methods: First of all, the testing device model was built based on a 252Cf neutron source. Three kinds of models (the thicknesses of the moderation layer, the protective layers of the neutron and gamma ray) are calculated respectively using the MCNP program for the shielding performance testing device. The GEANT4 program was used for the key moderation layer to verify the results obtained by the MCNP program. Results: Through the analysis of simulation results, we obtained optimal shielding materials and the thicknesses of material layer: moderator layer material is paraffin wax, which having a thickness of 8 cm, neutron shielding material is polyethylene, which having a thickness of 38 cm, and γ protective layer material is iron, which having a thickness of 11 cm. Conclusion: Simulation results show that the proposed shielding performance testing device can meet the requirements of neutron moderator, neutron protection and photon protection.

Key words: 252Cf neutron source, Shielding performance testing device, MCNP, Moderator material

HE Dan, SONG Yingming, ZOU Shuliang, XU Shoulong, WANG Xiaodong, ZHU Zhichao, TAN Zhengan, HE Zhifeng, WANG Xinlin. Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source [J].Nuclear Techniques, 2015, 38(9): 90604-090604.

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Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source

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