1. I. A. E. A. (IAEA), “Research reactor core conversion guidebook - Volume 1: Summary,” Tech. Rep. (1992).
2. J. Matos, E. Pennington, K. Freese, and W. Woodruff, “Safety-related benchmark calculations for MTR-type reactors with HEU, MEU and LEU fuels,” Tech. Rep. (1992).
3. Simulation of loss-of-flow transients in research reactors
4. S. EL Morshdy, “Transient thermal hydraulic modeling for off site power loss in nuclear reactors,” (2002).
5. Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code