MCNPx Calculation of Neutron Response for an Extended Range Neutron Rem M eter

SU You-wu; ZHU Xiao-long; Li  Wu—yuan

doi:10.11804/NuclPhysRev.22.02.198

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Article Navigation > Nuclear Physics Review > 2005 > 22(2): 198-199

SU You-wu, ZHU Xiao-long, Li Wu—yuan. MCNPx Calculation of Neutron Response for an Extended Range Neutron Rem M eter[J]. Nuclear Physics Review, 2005, 22(2): 198-199. doi: 10.11804/NuclPhysRev.22.02.198

Citation:

SU You-wu, ZHU Xiao-long, Li Wu—yuan. MCNPx Calculation of Neutron Response for an Extended Range Neutron Rem M eter[J]. Nuclear Physics Review, 2005, 22(2): 198-199. doi: 10.11804/NuclPhysRev.22.02.198

MCNPx Calculation of Neutron Response for an Extended Range Neutron Rem M eter

doi: 10.11804/NuclPhysRev.22.02.198

Institute of Modern Physic,Chinese Academy of Sfiences,Lanzhou 730000,China

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2005-06-20

Abstract

The responses of two extended neutron rein counters as function of neutron energy was ca1cuated Monte Carlo code，MCNPx，was applied in the calculations．Isotropic neutron incidence was employed．The results show that the neutron response is independent on thickness of lead 1aver at low energies，and it is clearly increased with thickness of lead layer at high energies．Although tt1e shape of the response curve does not completely agree with the H (10) curve in ICRP 74 report ，the resuhs obtained give good bases for the practical use of the new instrument in high—energy neutron fields
- MCNPx,
- high energy neutron：rem counter,
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通讯作者: 陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

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