LMFBR fuel analysis. Task B: Post-accident heat removal. Final report, October 1, 1976--September 30, 1977

Technical Report · Sat Oct 01 04:00:00 EDT 1977

OSTI ID:5074003

Castle, J; McDonough, J M; Ostrander, N C; Catton, I

This Task B annual report focuses on the interaction of concrete structures and core debris which may be released in a LMFBR core disruptive accident. A heat transfer calculational technique is described and applied to the exchange of energy from hot core debris to the concrete. Predictions are compared to several test conditions for which data are available. Calculations are made of the extent to which debris can penetrate the structure prior to solidification. The Clinch River plant and the FFTF are used as two examples in the calculations. The numerical characteristics of the Sandia INTER and Westinghouse WAYER post-accident heat removal codes are scrutinized. An evaluation is made of the heat transfer characteristics exhibited in material interaction tests conducted at the Aerospace Corporation.

• Research Organization: California Univ., Los Angeles (USA). School of Engineering and Applied Science
• OSTI ID: 5074003
• Report Number(s): NUREG/CR-0012
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
BUILDING MATERIALS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES