1. Blair, S., 2003. Thermal Hydraulic Performance Analysis of a Small Integral Pressurized Water Reactor Core, Master of Science in Nuclear Engineering and Nuclear Engineer, MIT, Department of Nuclear Engineering.
2. EPRI-NP-2609, 1982. Parametric Study of CHF Data, Volume 2: A generalized Subchannel CHF Correlation for PWR and BWR Fuel Assemblies”, Electric Power Research Institute, Palo Alto, California, Prepared by Heat Transfer Research Facility, Department of Chemical Engineering, Columbia University, New York.
3. ESBWR Design Control Document, 2007. Tier 2, Chapter 4 “Reactor”. 26A6642AP. Revision 4. Available at NRC electronic library, ADAMS No. ML072900630.
4. Fawcett, R.M., 2004. (GNF), to Greenspan, E. (University of California Berkeley), Personal Communication. November 2004.
5. Steady state Thermal Hydraulic Analysis of Hydride-fueled BWRs;Ferroni,2006