1. “ENDF/B Summary Documentation,” BNL-NCS-17541 (ENDF-201), 4th ed. (ENDF/B-VI), P. F. ROSE, Ed. Brookhaven National Laboratory (Oct. 1991; Release-2, 1993; Release-3, 1995).
2. R. E. McFarlane, “NJOY91.91: A Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Evaluated Nuclear Data,” ORNL PSR-171, Oak Ridge National Laboratory (1993).
3. R. C. LITTLE, “High-Temperature MCNP Cross Sections,” X-6-IR-87-505, Los Alamos National Laboratory, Radiation Transport Group (Oct. 1987).
4. Benchmark Calculations for the Doppler Coefficient of Reactivity
5. “MCNP-A General Monte Carlo Code for N-Particle Transport, Version 4A”, LA-12624, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (1993).