MC Calculation of Neutron Response for an Extended Range Multisphere Neutron Spectrometer
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Graphical Abstract
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Abstract
The responses of an extended range Multisphere Neutron Spectrometer as function of neutron energy were calculated by Monte Carlo code，FLUKA. The results show that peak value of the response curve shift to the right with the increasing of polyethylene thickness, but decreases in the high energy region. For neutron with energy >20 MeV, the response of polyethylene moderator will be decreased to be a very low level no matter what size it is. For neutron energies below 1 MeV, the response curve of moderator with auxiliary materials behave like the one of polyethylene moderator, but above 20 MeV the responses increase signi cantly due to increasing (n, xn) cross-sections of auxiliary materials. Based on the present discussion, the size of an extended range multisphere neutron spectrometer can be determined.
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