Integrated Fuel-Coolant Interaction code: Assessment of stand-alone version 6.0

Technical Report · Sun Aug 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10180131· OSTI ID:10180131

Davis, Jr, F J

Short communication.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 10180131
• Report Number(s): SAND-93-1872C; CONF-931079-2; ON: DE93019436; TRN: 93:020024
• Resource Relation: Conference: 21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR ACCIDENTS
FUEL-COOLANT INTERACTIONS
I CODES
CORIUM
WATER
FLUID FLOW
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
COMPUTERIZED SIMULATION
220900
990200
MATHEMATICS AND COMPUTERS