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Summary and Conclusion

Many IAEA Member States have an interest in the development of nuclear power for electric generation and heat production. A desk-top nuclear plant simulator for the principle types of water cooled reactors (PWR, BWR, PHWR and advanced LWR) could form a key element for the education of nuclear engineers.

The IAEA has sponsored a program, by introducing a desk-top simulator for generic nuclear plants in the size range of 600 MWe suitable for these countries. An advanced PWR model was presented with verification work conducted for a medium sized LOCA. The results are generally consistent with predictions using very detailed thermalhydraulics codes. The ARS simulator is planned to be used in a IAEA sponsored training workshop and will be distributed upon request to interested Member States.

 

References

1. IAEA-TECDOC-881, "Design and Development Status of Small and Medium Rector Systems 1995", May 1996.
2. L. C. PO and J. M. LINK, "PCTRAN-3 The 3rd Generation of Personal Computer-Based Plant Analyzer for Severe Accident Management", Proceedings of the 4th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, Taipei, Taiwan, April 5-8, 1994.
3. H. Tirkkonen, et al, "Severe Accident Simulation at Olkiluoto", Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics", September 10 - 15, 1995, Saratoga Springs, U.S.A., NURETH-7, NUREG/CP-0142, p. 2438.
4. B. E. BOYACK AND J. F. LIME, "Analysis of an AP600 Intermediate-Size Loss-of-Coolant Accident", Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics, September 10 - 15, 1995, Saratoga Springs, U.S.A., NURETH-7, NUREG/CP-0142, p. 1153.



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