1. Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN;Ammirabile;Nucl. Eng. Des.,2010
2. Basile, D., Beghi, M., Chierici, R., Salina, E., Brega, E., 1987. COBRA-EN: Code System for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores.
3. Application of the Monte Carlo Method for the Calculation of Safety Related Reactor Physics Parameter for Power Reactor with Consideration of Detailed Burnup Distributions;Bernnat,2000
4. Forced convection heat transfer to water at near-critical temperatures and supercritical pressures;Bishop;Chem. Eng. Symp. Ser.,1965
5. Briesmeister, J.F., 2000. Monte Carlo N-Particle (MCNP) Transport Code, 4c ed. Los Alamos National Laboratory.