Reliability of Monte Carlo simulations in modeling neutron yields from a shielded fission source

摘要

Using the combination of a neutron-sensitive ~6Li glass scintillator detector with a neutron-insensitive ~7Li glass scintillator detector, we are able to make an accurate measurement of the capture rate of fission neutrons on ~6Li. We used this detector with a ~(252)Cf neutron source to measure the effects of both non-borated polyethylene and 5% borated polyethylene shielding on detection rates over a range of shielding thicknesses. Both of these measurements were compared with MCNP calculations to determine how well the calculations reproduced the measurements. When the source is highly shielded, the number of interactions experienced by each neutron prior to arriving at the detector is large, so it is important to compare Monte Carlo modeling with actual experimental measurements. MCNP reproduces the data fairly well, but it does generally underestimate detector efficiency both with and without polyethylene shielding. For non-borated polyethylene it underestimates the measured value by an average of 8%. This increases to an average of 11% for borated polyethylene.