Monte Carlo analysis of energy deposition in a cryogenic neutron detector

In this paper we present the results of modeling the absorption of neutrons in blocks of B-10 and (LiF)-Li-6 with the MCNP-PoliMi code. MCNP-PoliMi correctly links secondary gamma ray production to the neutron interaction type and permits an accurate accounting of the energy deposited as a result of capture reactions (kinetic energy of reaction products), the energy deposited by recoiling ions (elastic and inelastic scattering), and the energy deposited by de-excitation gammas resulting from inelastic scattering on an event-by-event basis. The response to spontaneous fission sources, as well as monoenergetic sources, is presented.