4. METHOD OF SOLUTION
The Monte Carlo method represents a Neumann series solution of the integral transport equation. Included in the sampling techniques are splitting, Russian Roulette, statistical estimation, and a method of importance sampling in the source angular distribution.
The code provides for the calculation of the energy and angular distribution of the scattered neutron or gamma-ray flux, the total scattered neutron or gamma-ray flux and dose rates, and the unscattered neutron or gamma-ray flux and dose rate.
A library of cross sections which can be easily changed is packaged with the code.