IFCI 7.0 Models and Correlations

Technical Report · Sat May 01 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/7685· OSTI ID:7685

Reed, A W ^[1]; Schmidt, R C; Young, M F

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1. Sandia National Laboratories

The Integrated Fuel-Coolant Interaction Code (IFCI) is a best-estimate computer program for analysis of phenomena related to mixing of molten nuclear reactor core material with reactor coolant (water). The stand-alone version of the code, IFCI 7.0, has been designed for analysis of small- and intermediate-scale experiments in order to gain insight into the physics (including scaling effects) of molten fuel-coolant interactions. The code's methods, models, and correlations are being assessed. This report describes the flow regime, friction factor, and heat-transfer models used in the current version of IFCI (IFCI 7.0).

• Research Organization: Sandia National Labs., Albuquerque, NM (US); Sandia National Labs., Livermore, CA (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 7685
• Report Number(s): SAND99-1000
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COOLANTS
CORIUM
FRICTION FACTOR
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
I CODES
WATER COOLED REACTORS