References

General References

1. F. E. Dunn and F. G. Prohammer, “SASSYS Analysis of Degraded Shut Down Heat Removal Performance in LMFBRs,” ASME Paper No. 82 WA/HT 37, 1982.
2. F. E. Dunn and F. G. Prohammer, “The SASSYS LMFBR Systems Analysis Code,” Proceedings of the 10th IMACS World Conference on Systems Simulation and Scientific Computation, Vol. 4, Montreal, Canada, pp. 127-129, August, 1982.
3. F. E. Dunn et al., “The SASSYS 1 LMFBR Systems Analysis Code,” Proceedings of the International Topical Meeting on Fast Reactor Safety, American Nuclear Society, Knoxville, TN, April 21 25, 1985.
4. D. K. Warinner and F. E. Dunn, “SASSYS 1 Computer Code Verification with EBR II Test Data,” Proceedings of the International Topical Meeting on Fast Reactor Safety, American Nuclear Society, Knoxville, TN, April 21 25, 1985.
5. F. E. Dunn, “The SAS4A/SASSYS l Sodium Boiling Model for LMFBR Whole Core Analysis,” Heat Transfer - Denver 1985, AIChE Symposium Series, No. 245, Vol. 81, 1985.
6. F. E. Dunn et al., “LMR Thermal Hydraulics Calculations in the U.S.,” Proceedings of the International Topical Meeting on Advances in Reactor Physics, Mathematics and Computation, Paris, France, April 27 30, 1987.
7. D. J. Hill, “SASSYS Analysis of EBR-II SHRT Experiments,” Trans. Am. Nucl. Soc., 55, 421, 1987.
8. F. E. Dunn, “LMR Thermal Hydraulics Calculations in the U.S.,” Nucl. Sci. Eng., 100, 558, 1988.
9. F. E. Dunn and T. Y. C. Wei, “Simulating Operational Transients with the SASSYS 1 LMR Systems Analysis Code,” 1988 SCS Simulators Conference, Society for Computer Simulation, Orlando, FL, April 18-21, 1988.
10. F. E. Dunn and T. Y. C. Wei, “The Role of SASSYS 1 in LMR Safety Analysis,” Proceedings of the International Topical Meeting on Safety of Next Generation Power Reactors, American Nuclear Society, Seattle, WA, May 1 5, 1988.
11. D. J. Hill, “SASSYS Validation Studies,” Proceedings of the International Topical Meeting on Safety of Next Generation Power Reactors, American Nuclear Society, Seattle, WA, May 1 5, 1988.
12. F. E. Dunn, “Decay Heat Calculations for Transient Analysis,” Trans. Am. Nucl. Soc., 60, 633, 1989.
13. J. P. Herzog, “SASSYS Validation with the EBR II Shutdown Heat Removal Tests,” Trans. Am. Nucl. Soc., 60, 730, 1989.
14. F. E. Dunn and J. P. Herzog, “Thermal-Hydraulic Impact of Failure of Highly Irradiated Fuel Pins on LMR Passive Safety,” Trans. Am. Nucl. Soc., 62, 673, 1990.
15. F. E. Dunn, “Consequences of Pipe Ruptures in Metal Fueled, Liquid Metal Cooled Reactors,” Proceedings of the International Fast Reactor Safety Meeting, American Nuclear Society, Snowbird, UT, August 12-16, 1990.
16. J. E. Cahalan and T. Wei , “Modeling Developments for the SAS4A and SASSYS Computer Codes,” Proceedings of the International Fast Reactor Safety Meeting, American Nuclear Society, Snowbird, UT, August 12-16, 1990.
17. P. L. Garner et al., "Development of a Graphical User Interface Allowing Use of the SASSYS 1 LMR Systems Analysis Code as an EBR II Interactive Simulator", Proceedings of International Topical Meeting on Advanced Reactors Safety, American Nuclear Society, Pittsburgh, PA, pp. 282 289, April 17 21, 1994.
18. J. E. Cahalan et al., "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, Pittsburgh, PA, April 17 21, 1994.