References
- “MCNPtm—A General Monte Carlo Code N-Particle Transport Code, Version 4C,” LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
- C. CHEN, “Development of SUNMAN: A Graphically Driven Steady State Neutronic and Thermal Hydraulic Model of the Nuclear Science Center Reactor at Texas A&M University,” PhD Dissertation, Texas A&M University (1997).
- D. G. FOSTER, Jr., and E. D. ARTHUR, “Average Neutron Properties of Prompt Fission Products,” LA-9168-MS, Los Alamos National Laboratory (1982).
- P J. GRIFFIN and J. G. KELLY, “SNL-SAND-II: Neutron Flux Spectra Determination by Multiple Foil Activation— Iterative Method,” PSR-345, Radiation Safety Information Computational Center (1994).