Fast Neutron Attenuation Analysis for a SNAP Reactor Shadow Shield Using the Flexible Monte Carlo Code, FMC-N

摘要

Calculations were performed to demonstrate the feasibility of using the G. E. A. N. P. Flexible Monte Carlo Code, FMC-N, for SNAP shielding analysis. The SNAP 10A reactor-shield configuration, with the original design shield, was used as the calculational model. The results of the calculation were somewhat inconclusive due to the lack of any P-actual comparison between FMC calculations and experimental data for LiH systems. However, the ability of the code to calculate such things as flux, reflector scattering contribution, leakage effects, spectra, and attenuation between shield bottom and dose plane, was demonstrated. Comparisons between the FMC results and previous calculations using ray tracing techniques pointed out areas where the discrepancies in the methods of calculation were sufficiently large to warrant further study.