Verification and Validation of MCNP6.1 Neutron Protection Factor Estimates of an Armored Vehicle Surrogate Using the White Sands Missile Range Fast Burst Reactor
Journal Article - Open Access
Defense Threat Reduction Agency Ft. Belvoir United States
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Building upon past successful verification and validation V and V efforts forMCNP6.1-derived radiation protection factor RPF estimates, this experiment sought to V and V MCNP6.1-estimated neutron protection factor NPF values for an armored vehicle surrogate when exposed to a 235U fission spectrum at a horizontal distance of 12 ft. The neutron source for both the experimental and computational analyses was the White Sands Missile Range Fast Burst Reactor. Neutron fluxes for both shielded and unshielded configurations were measured using a Bonner sphere spectrometer and LiIEu scintillator, and the spectra were unfolded using MAXED, a maximum entropy deconvolution code. The computed neutron spectra for both configurations were likewise tallied by MCNP6.1, and both computational and experimental neutron flux results were converted to total ambient dose equivalent H10. The dose values facilitated NPF calculations for the armored surrogate, which were experimentally-determined to be 1.22 0.06, while MCNP6.1 estimated a value of 1.18 0.02. This NPF value agreement strongly supports the V and V and eventual accreditation of MCNP6.1for radiation protection factor assessments of military vehicles.
- Combat Vehicles
- Nuclear Radiation Shielding, Protection and Safety