1. A Monte Carlo Learning/Biasing Experiment with Intelligent Random Numbers;Booth;Nuclear Science and engineering,1986
2. MCNP — A General Monte Carlo Code for Neutron and Photon Transport,1986
3. Butler, J. (1989) Personal communication.
4. Industrial Needs for Radiation Transport Calculations;Butler,1990
5. Version of MCNP to Treat Perturbations;Carter,1977