1. Nuclear Reactor Theory;Bell,1970
2. Cross section recondensation via generalized energy condensation theory;Douglass;Annals of Nuclear Energy,2011
3. Specification for a 1-dimensional gas-cooled reactor benchmark problem for neutron transport. American Nuclear Society 2011 National Meeting, Hollywood, FL;Douglass;Transaction of the American Nuclear Society,2011
4. Kelly, D.J., 1995. Depletion of a BWR lattice using the RACER continuous energy Monte Carlo code. In: Proceedings of the International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, Portland, Oregon, April 30–May 4, vol. 2. American Nuclear Society, p. 1011.
5. Lewis, E.E., Miller Jr., W.F., 1984. Computational Methods of Neutron Transport. John Wiley & Sons, New York (Republished by Am. Nucl. Soc. 1993).