References
- “Safety Analysis Report for TRIGA Mark II Reactor,” IJS-5823, Jozef Stefan Institute (1992).
- I. MELE, M. RAVNIK, and A. TRKOV, “TRIGA Mark II Benchmark Experiment, Part I: Steady-State Operation”, Nucl, Technol., 105, 37 (1994).
- J. R. ASKEW, F. J. FAYERS, and P. B. KEMSHELL, “A General Description of the Lattice Code WIMS”, J. Br. Nucl. Energy Soc., 5, 564 (Oct. 1966).
- M. RAVNIK, M. STREBL, H. BOECK, A. TRKOV, and I. MELE, “Determination of the Burn-Up of TRIGA Fuel Elements by Calculation and Reactivity Experiments”, Kerntechnik, 57, 5, 291 (1992).
- “American National Standard Design Objectives for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Stations,” ANSI-N210-1976, American National Standards Institute (1976).
- J. F. BRIESMEISTER, “MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A,” LA-12625-M, Los Alamos National Laboratory (1993).
- “MCNP, Version 4, Standard Neutron Cross Section Data Library Based in Part on ENDF/B-V,” RSIC-DLC-105, Oak Ridge National Laboratory (1994).
- R. KINSEY, “ENDF-201 ENDF/B Summary Documentation, 3rd Edition (ENDF/B-V),” BNL-NCS-17541, Brookhaven National Laboratory (1979).
- “WIMS-D/4 Program Manual,” Organization for Economic Cooperation and Development Nuclear Energy Agency Data Bank (1990).
- “Update of the WIMS-D4 Nuclear Data Library,” INDC-290, International Atomic Energy Agency (1993).
- M. RAVNIK and I. MELE, “Optimal Fuel Utilization in TRIGA Reactor with Mixed Core”, Proc. Int. Reactor Physics Conf., Jackson Hole, Wyoming, September 18–22, 1988, Vol. 11, p. 483, American Nuclear Society (1988).
- M. RAVNIK, “Safety Parameters of Mixed TRIGA Cores”, Proc. Workshop Reactor Physics Calculations for Applications in Nuclear Technology, Trieste, Italy, February 12–March 16, 1990, p. 398, World Scientific.