Summary and Conclusion
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.
IAEA-TECDOC-881, "Design and Development Status of Small
and Medium Rector Systems 1995", May 1996.
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
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.
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,