1.4. References¶
1-1. Y. S. Tang, R. D. Coffield, Jr., R. A. Markley, “Thermal Analysis of Liquid Metal Fast Breeder Reactors,” Westinghouse Electric Corporation, Madison, Pennsylvania, American Nuclear Society Publications, 1978.
1-2. H. A. Bethe and J. H. Tait, “An Estimate of the Order of Magnitude of the Explosion When the Core of a Fast Reactor Collapses,” RHM-56-113, April 1956.
1-3. A. E. Waltar, A. Padilla, Jr., and R. J. Shields, “MELT-II, A Two-Dimensional Neutronics-Heat Transfer Program for Fast Reactor Safety Analysis,” Unpublished information, Hanford Engineering Development Laboratory, 1972.
1-4. K. K. Tabb, C. H. Lewis, L. D. O’Dell, A. Padilla, Jr., D. E. Smith, and N. P. Wilburn, “MELT-IIIB: An Updated Version of the MELT Code,” Unpublished information, Hanford Engineering Development Laboratory, April 1979.
1-5. J. C. Carter, et al., “SAS1A, A Computer Code for the Analysis of Fast-Reactor Power and Flow Transients,” ANL-7606, Argonne National Laboratory, October 1970.
1-6. F. E. Dunn, et al., “The SAS2A LMFBR Accident-Analysis Computer Code,” ANL-8138, Argonne National Laboratory, October 1974.
1-7. M. G. Stevenson, W. R. Bohl, F. E. Dunn, T. J. Heames, G. Hoppner, and L. L. Smith, “Current Status and Experimental Basis of the SAS LMFBR Accident Analysis Code System,” Proc. Fast Reactor Safety Meeting, American Nuclear Society, CONF-740401-P3, pp. 1303-3121, Beverly Hills, CA, April 2-4, 1974.
1-8. J. E. Cahalan, A. M. Tentner, and E. E. Morris, “Advanced LMR Safety Analysis Capabilities in the SASSYS-1 and SAS4A Computer Codes,” Proceedings of the International Topical Meeting on Advanced Reactors Safety, American Nuclear Society, Vol. 2, pp. 1038-1045, Pittsburgh, PA, April 17-21, 1994.
1-9. F. E. Dunn, J. E. Cahalan, D. Hahn, H. Y. Jeong, “Whole Core Sub-Channel Analysis Verification with EBR-II SHRT-17 Test,” Proc. 2006 Int’l Congress on Advances in Nuclear Power Plants, Reno, NV, June 6-8, 2006.
1-10. G. Birgersson, et al., Unpublished information, Argonne National Laboratory, 1988.
1-11. F. E. Dunn, et al., Unpublished information, Argonne National Laboratory, 1987.
1-12. C. E. Till, “Fast Reactor Directions: The LMR Integral Fast Reactor Program at Argonne,” Proceedings of the International Fast Reactor Safety Meeting, Snowbird, Utah, August 12-16, 1990.
1-13. Argonne National Laboratory, Unpublished information, 1996.
1-14. J. Sackett, et al., “EBR-II Test Programs,” Proceedings of the International Fast Reactor Safety Meeting, Snowbird, Utah, August 12-16, 1990.
1-15. T. H. Fanning, ed., “The SAS4A/SASSYS‑1 Safety Analysis Code System,” ANL/NE-12/4, Nuclear Engineering Division, Argonne National Laboratory, January 31, 2012.
1-16. F. E. Dunn, Unpublished information, Argonne National Laboratory, 1993.
1-17. D. Mohr, et al., “Loss-Of-Primary-Flow-Without-Scram Tests: Pretest Predictions and Preliminary Results,” Nuclear Engineering and Design, 101, 1987.
1-. T. Sofu and L. L. Briggs, “Benchmark Specifications for EBR-II Shutdown Heat Removal Tests,” Proc. Int’l Congress on Advances in Nuclear Power Plants, ICAPP 2012, Chicago, IL, June 24-28, 2012.
1-19. IFR Properties Evaluation Working Group, “Handbook of Properties of Metallic Fuels,” Argonne National Laboratory, Idaho Falls, Idaho, June, 1988.
1-20. T. H. Hughes and J. M. Kramer, “The FPIN2 Code - An Application of the Finite Element Method to the Analysis of the Transient Response of Oxide and Metal Fuel Elements,” Conference on the Science and Technology of Fast Reactor Safety, British Nuclear Energy Society, Guernsey, May 12-16, 1986.
1-21. J. P. Herzog and K. J. Miles, Unpublished information, Argonne National Laboratory, 1989.
1-22. A. M. Tentner, Unpublished information, Argonne National Laboratory, April, 1993.
1-23. A. M. Tentner and Kalimullah, Unpublished information, Argonne National Laboratory, 1993.
1-24. E. E. Morris and A. M Tentner, Unpublished information, Argonne National Laboratory, 1994.