1. Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., O'Dell, R.D., Walters, W.F., 1995. DANTSYS: a diffusion accelerated neutral particle transport code system. Report LA-12969-M, Los Alamos National Laboratory, Los Alamos, NM.
2. Breismeister, J.F., 1993. MCNP: a general Monte Carlo N-particle transport code. Report LA-12625-M, Los Alamos National Laboratory, Los Alamos, NM.
3. BUGLE, 1996. BUGLE-96: coupled 47 neutron, 20 gamma-ray group cross section library derived from ENDF/B-VI for LWR shielding and pressure vessel dosimetry applications. Technical Report DLC-185, Radiation Shielding Information Center, Oak Ridge National Laboratory, Oak Ridge, TN.
4. Congedo, T.V., Ruddy, F.H., McLaughlin, D.F., 1993. Neutron transport modeling in support of prompt gamma neutron activation for environmental analysis. Technical Report 93-7TD1-PGEXT-P2, Westinghouse Science and Technology Center.
5. DOE, 1994. Multispectral neutron logging: a new generation pulsed-neutron induced gamma-ray multi-spectra logging system for in situ mapping of contaminants, in characterization, monitoring and sensor technology integrated program. Technical Report DOE/EM-0156T, US Department of Energy, Office of Environmental Management, Washington, DC.