1. Briesmeister, J.F., 1997. MCNP — a general purpose Monte Carlo n-particle transport code version 4b, LA-12625-M
2. A method for measuring thermal neutron absorption and transport cross sections;Bussian;Nucl. Geo.,1991
3. Mickael, M.W, 1988. Monte Carlo simulation of dual-spaced neutron porosity well logging tool responses. Ph.D. Thesis, NCSU
4. Tallavarjula, S., 1995. Thermal neutron cross section measurement for geological materials. Ph.D. Thesis, NCSU
5. Tittle, C.W., Crawford, G.W., 1983. Measuring the thermal neutron absorption cross section of rocks. Log Analy