Interaction and penetration of heated UO/sub 2/ with limestone concrete. [LMFBR]
Conference
·
OSTI ID:6342446
To safeguard the environment against radiological releases, the major question of concern in PAHR safety assessment, following an HCDA, involves confinement and dilution of the molten core-debris. Significant to the study is the directional growth of the core-debris in the concrete foundation of the reactor building or the concrete below the reactor cavity. The real material experiments were carried out in the test apparatus shown. Casts of CRBRP limestone concrete were prepared in graphite cylinders, each having an internal diameter of 8.9 cm and a depth of 30.5 cm. The 17.8-cm-deep concrete samples were allowed to cure for at least 28 days. Experiments were conducted within two months of curing time. The cavity above concrete was packed with 3 kg of pure UO/sub 2/ particles (1 to 3 mm). A uranothermic mixture was placed on the top of UO/sub 2/ powder. Heating and possible melting of UO/sub 2/ was achieved resistively after the ignition of the thermite. Total experimental time was about 60 minutes, during which time a maximum electrical power input of 1.8 watts/gr was applied to the UO/sub 2/. Three gas samples were taken at temperatures of 100, 600, and 950/sup 0/C, measured in the plane of the No. 2 thermocouple. Selection of three temperatures were to study the amount and the type of gases released from different phases of concrete.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6342446
- Report Number(s):
- CONF-820717-6; ON: DE83008500
- Country of Publication:
- United States
- Language:
- English
Similar Records
Simulation of heat and mass transfer processes in molten core debris-concrete systems. [LMFBR]
LMFBR safety
Downward penetration of hot UO/sub 2/ into basalt concrete
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6111111
LMFBR safety
Technical Report
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6475685
Downward penetration of hot UO/sub 2/ into basalt concrete
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6219810
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
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CHEMICAL REACTIONS
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
STRESSES
TEST FACILITIES
THERMAL STRESSES
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
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CHEMICAL REACTIONS
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
STRESSES
TEST FACILITIES
THERMAL STRESSES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES