MCNPx Calculation of Neutron Response for an Extended Range Neutron Rem M eter
doi: 10.11804/NuclPhysRev.22.02.198
- Received Date: 1900-01-01
- Rev Recd Date: 1900-01-01
- Publish Date: 2005-06-20
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Key words:
- MCNPx /
- high energy neutron:rem counter /
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
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 |