Application of the IFCI (Integrated Fuel-Coolant Interaction) code to a FITS-type pouring mode experiment

Conference · Sun Jan 01 04:00:00 EST 1989

OSTI ID:5861970

Young, M. F.

The phenomenon of molten fuel-coolant interaction (FCI) is of considerable interest in many industrial processes where hot molten material may come in contact with water, including the pulp and paper, aluminum, steel, and nuclear power industries. The nature of the FCIs can range from mild film boiling, through energetic boiling, up to a violent vapor explosion. In the nuclear power industry, FCIs are of interest because of their possible consequences during hypothetical light water reactor core meltdown accidents. 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 large scale using a two-dimensional, four-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. The hydrodynamic method and physical models used in IFCI are discussed. Results from a test problem simulating a generic pouring mode experiment are presented. 39 refs., 10 figs., 1 tab.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5861970
• Report Number(s): SAND-89-1692C; CONF-890739-2; ON: DE89015392
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
BOILING
COMPUTER CODES
CORIUM
ENERGY TRANSFER
EQUATIONS
EXPLOSIONS
FILM BOILING
FLUID MECHANICS
FLUIDS
FUEL-COOLANT INTERACTIONS
GASES
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMIC MODEL
HYDRODYNAMICS
I CODES
MATHEMATICAL MODELS
MECHANICS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PARTICLE MODELS
PHASE TRANSFORMATIONS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR SAFETY
SAFETY
STATISTICAL MODELS
THERMAL POWER PLANTS
THERMODYNAMIC MODEL
VAPORS