IFCI: An Integrated code for calculation of all phases of Fuel-Coolant Interactions
Technical Report
·
OSTI ID:5654126
The IFCI (Integrated Fuel-Coolant Interaction) code was developed to investigate the interaction of hot molten materials with water in as mechanistic a manner as possible. This report describes the key features of IFCI, such as dynamic fragmentation and surface area transport, and describes the results of the first IFCI test problem. The test problem is a simulation of an experiment from the Fully Instrumented Test Series (FITS) in which 20 kg of molten iron-alumina thermite was poured into a tank of water. 30 refs., 16 figs., 2 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5654126
- Report Number(s):
- NUREG/CR-5084; SAND-87-1048; ON: TI88005325
- Country of Publication:
- United States
- Language:
- English
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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
COMPUTER CODES
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FINITE DIFFERENCE METHOD
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
I CODES
INFORMATION
ITERATIVE METHODS
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NUMERICAL DATA
NUMERICAL SOLUTION
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THEORETICAL DATA
WATER COOLED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
COMPUTER CODES
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FINITE DIFFERENCE METHOD
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
I CODES
INFORMATION
ITERATIVE METHODS
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NUMERICAL DATA
NUMERICAL SOLUTION
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THEORETICAL DATA
WATER COOLED REACTORS