Abstract
There is a desire from the radiation detection community to develop a low-cost method to detect neutron radiation. One potential solution is to measure the 478 keV gamma-ray from the10B(n, α) reaction using a spectroscopic gamma-ray detector. Experiments and Monte Carlo N-Particle 6.2 radiation transport simulations were performed for a NaI(Tl) detector surrounded with natural isotopic composition boron carbide powder. The neutron source for the experimental measurements was241Am–Be. Additional MCNP simulations were performed using a240Pu spontaneous fission neutron source. The experimental results were compared against3He based measurements and found to be 70% as efficient as the3He system. The total cost of this modification to an existing NaI(Tl) detector was $65.12. The optimal10B-NaI(Tl) system design when measuring240Pu was determined to consist of a 0.5 cm endcap of boron carbide and 6 cm of high-density polyethylene for neutron moderation.
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