IFCI: An integrated code for calculation of all phases of fuel-coolant interactions

Conference · Thu Dec 31 23:00:00 EST 1987

OSTI ID:5122264

Young, M F

A problem of considerable interest in reactor safety is the possibility of molten fuel-coolant interactions (FCIs) occurring during a hypothetical light water reactor core meltdown accident. These interactions may occur under a variety of conditions either within the reactor vessel or in the reactor cavity. The IFCI computer code is being developed to investigate the FCI problem at reactor scale in as mechanistic a manner as possible. This paper discusses the main features of the IFCI code and the results of the first test problem run with IFCI.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5122264
• Report Number(s): SAND-87-1048C; CONF-880724-8; ON: DE88005105
• Country of Publication: United States
• Language: English

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