FARO base case post-test analysis by COMETA code

Technical Report · Fri Sep 01 00:00:00 EDT 1995

DOI:https://doi.org/10.2172/115086· OSTI ID:115086

Annunziato, A.; Addabbo, C. ^[1]

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1. Joint Research Centre, Ispra (Italy)

The paper analyzes the COMETA (Core Melt Thermal-Hydraulic Analysis) post test calculations of FARO Test L-11, the so-called Base Case Test. The FARO Facility, located at JRC Ispra, is used to simulate the consequences of Severe Accidents in Nuclear Power Plants under a variety of conditions. The COMETA Code has a 6 equations two phase flow field and a 3 phases corium field: the jet, the droplets and the fused-debris bed. The analysis shown that the code is able to pick-up all the major phenomena occurring during the fuel-coolant interaction pre-mixing phase.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; American Nuclear Society (ANS), La Grange Park, IL (United States); American Institute of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers (ASME), New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
• OSTI ID: 115086
• Report Number(s): NUREG/CP-0142-Vol.3; CONF-950904-Vol.3; ON: TI95017079; TRN: 95:022986
• Resource Relation: Conference: 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Volume 3, Sessions 12-16; Block, R.C.; Feiner, F. [comps.] [American Nuclear Society, La Grange Park, IL (United States)]; PB: 1001 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
CORIUM
COOLING
WATER COOLED REACTORS
SAFETY ANALYSIS
REACTOR CORE DISRUPTION
C CODES
HYDRAULICS
REACTOR SAFETY
PROCEEDINGS
MOLTEN METAL-WATER REACTIONS
NUMERICAL DATA
NUMERICAL ANALYSIS