Light Water Reactor Safety Research Program. Semiannual report, October 1982-March 1983. [Molten fuel/concrete interaction; core melt-coolant interaction; hydrogen detonation (Grand Gulf igniter)]
Technical Report
·
OSTI ID:7029959
The Molten Fuel/Concrete Interactions (MFCI) Study investigates the mechanism of concrete erosion by molten core materials, the nature and rate of generation of evolved gases, and the effects on fission product release. The Core Melt/Coolant Interactions (CMCI) Study investigates the characteristics of explosive and nonexplosive interactions between molten core materials and concrete, and the probabilities and consequences of such interactions. In the Hydrogen Program, the HECTR code for modelling hydrogen deflagration is being developed, experiments (including those in the FITS facility) are being conducted, and the Grand Gulf Hydrogen Igniter System II is being reviewed. All activities are continuing.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7029959
- Report Number(s):
- NUREG/CR-3734; SAND-84-0688; ON: DE84014717
- Country of Publication:
- United States
- Language:
- English
Similar Records
Light Water Reactor Safety Research Program. Semiannual report, October 1983-March 1984
Light Water Reactor Safety Research Program. Semiannual report, April-September 1983
Experimental results of the interaction of molten core materials with concrete
Technical Report
·
Fri Jan 31 23:00:00 EST 1986
·
OSTI ID:6077159
Light Water Reactor Safety Research Program. Semiannual report, April-September 1983
Technical Report
·
Wed Aug 01 00:00:00 EDT 1984
·
OSTI ID:6060969
Experimental results of the interaction of molten core materials with concrete
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7235077
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
CONCRETES
COOLANTS
CORIUM
DETONATIONS
ELEMENTS
ENRICHED URANIUM REACTORS
GRAND GULF-1 REACTOR
HYDROGEN
IGNITION
MATERIALS
MELTDOWN
NONMETALS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
CONCRETES
COOLANTS
CORIUM
DETONATIONS
ELEMENTS
ENRICHED URANIUM REACTORS
GRAND GULF-1 REACTOR
HYDROGEN
IGNITION
MATERIALS
MELTDOWN
NONMETALS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS