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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