REFERENCES
- L. ALI KHAN, I. H. BOKHARI, and K. M. AKHTAR, “Steady State Thermal Hydraulic Analysis of LEU Cores for Pakistan Research Reactor-1,” PINSTECH-122 (1991).
- C. F. OBENCHAIN, “PARET—A Program for the Analysis of Reactor Transient,” IDO-17282, AEC Research and Development Report (1969).
- R. SCOTT, Jr., C. L. HALE, and R. N. HAGEN, “Transient Tests of Fully Enriched Uranium Oxide Stainless Steel Plate Type C-Core in the SPERT-III Reactor,” IDO-17223, AEC Data Summary Report (1967).
- W. L. WOODRUFF, “A Kinetics and Thermal Hydraulics Capability for the Analysis of Research Reactor,” Argonne National Laboratory (1983).
- F. W. DITTUS and L. M. K. BOELTER, “Heat Transfer in Automobile Radiators of Tubular Tube,” U. Calif. Press Eng., 2, 13, 443 (1930).
- W. H. McADAMS, “Heat Transfer at High Rates to Water with Surface Boiling,” Ind. Eng. Chem. 41, 1945 (1949).
- J. E. METOS, E. M. PENNINGTON, K. E. FREESE, and W. L. WOODRUFF, “Safety-Related Benchmark Calculations for MTR Type Reactors with HEU, MEU and LEU Fuels,” Research Reactor Core Conversion Guidebook, Vol. 3, Analytical Verification, Appendixes G and H, IAEA, Vienna (1992).
- A. E. BERGLES and W. M. ROHSENOW, “The Determination of Forced Convection Surface Boiling Heat Transfer,” Trans. ASME 86 (Series C—J. Heat Transfer) (1964).
- “Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels,” IAEA-TECDOC-643 (1992).
- M. M. EL-WAKIL, Nuclear Heat Transport, International Textbook Company, Scranton, PA (1971).