Evaluation of materials for retention of sodium and core debris in reactor systems. Annual progress report, September 1977-December 1978. [LMFBR]
This report considers some of the consequences of a hypothetical core disruptive accident in a nuclear reactor. The interactions expected between molten core debris, liquid sodium, and materials that might be employed in an ex-vessel sacrificial-bed or in the reactor building are discussed. Experimental work performed for NRC by Sandia Laboratories and Hanford Engineering Development Laboratory on the interactions between liquid sodium and basalt concrete is reviewed. Studies of molten steel interactions with concrete at Sandia Laboratories and molten UO/sub 2/ interactions with concrete at The Aerospace Corporation are also discussed. The potential of MgO for use in core containment is discussed and refractory materials other than MgO are reviewed. Finally, results from earlier experiments with molten core debris and various materials performed at The Aerospace Corporation are presented.
- Research Organization:
- Aerospace Corp., El Segundo, CA (USA). Materials Sciences Lab.
- OSTI ID:
- 5959036
- Report Number(s):
- NUREG/CR-0900
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experimental investigations of long-term interactions of molten UO/sub 2/ with MgO and concrete at Argonne National Laboratory. [LMFBR]
Evaluation of materials for CRBRP core retention. Annual progress report
Hydrogen production during fragmented debris/concrete interactions. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6342478
Evaluation of materials for CRBRP core retention. Annual progress report
Technical Report
·
Sat Oct 01 00:00:00 EDT 1977
·
OSTI ID:7064656
Hydrogen production during fragmented debris/concrete interactions. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6607126
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
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CONCRETES
CORE CATCHERS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
THERMAL INSULATION
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CONCRETES
CORE CATCHERS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
THERMAL INSULATION
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES