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Wu Z.,University of South China | Wu Z.,Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities | Zou S.-L.,University of South China | Xu S.-L.,University of South China | Xu S.-L.,Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2016

The authenticity of simulation results obtained by using MCNP software has been confirmed. The mass attenuation coefficients and mean free path of several types of heavy metal oxide glasses and lead have been calculated By MCNP code in different energies of γ-ray. The same parameters were also calculated by XCOM code in the γ-rays energy region from 1 keV to 100 000 MeV. The Monte Carlo method has been demonstrated by comparing the experimental results and the simulation results from two types of software simulation. Research results show that, MCNP software based on Monte Carlo method could be used to calculate the shielding performance of heavy metal oxide glass. © 2016, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.


He D.,Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities | He D.,University of South China | Song Y.,University of South China | Zou S.,Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities | And 6 more authors.
He Jishu/Nuclear Techniques | Year: 2015

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. ©, 2015, Science Press. All right reserved.

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