1. TRIGA Spent-Fuel Storage Criticality Analysis
2. J. BRIESMEISTER, “MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A,” LA-12625-M, Los Alamos National Laboratory (1993).
3. “MCNPDAT, MCNP, Version 4, Standard Neutron Cross Section Data Library Based in Part on ENDF/B-V,” DLC-105, Oak Ridge National Laboratory (1994).
4. M. MAUCEC, “Description of DIMPLE S01A Model Developed with Monte Carlo Computer Code MCNP4A,” Private Communication, Jozef Stefan Institute (Jan. 1996).
5. A. TRKOV, “The Influence of the Basic Evaluated Data Files on Thermal Lattice Integral Parameters,” Private Communication, Jozef Stefan Institute (Jan. 1996).