In-reactor experiments on the cooling of fast reactor debris. [LMFBR]
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5512457
First-of-a-kind fission-heated experiments utilizing uranium oxide particles in liquid sodium have been performed to assess the nature of the passive heat transfer between fast reactor fuel debris and overlying coolant. The experiments were designed to simulate the situation following a core disruptive accident in which molten core material is quenched, fragmented, and is dispersed as beds of decay-heated particulate within the reactor vessel. In two of the experiments, threshold dryout of the fuel particulate was produced. During several runs, dryout was maintained for long periods (approx. 1 h) with only modest temperature increases, demonstrating that while bed dryout may be a necessary condition for remelting of the fuel, it is not always a sufficient condition.
- Research Organization:
- Sandia Labs., Albuquerque, NM
- OSTI ID:
- 5512457
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 46:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-reactor experiments with simulated LMFBR debris beds
In-reactor experiments on the cooling of fast reactor debris
Preliminary results from initial in-pile debris bed experiments. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7212670
In-reactor experiments on the cooling of fast reactor debris
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6871900
Preliminary results from initial in-pile debris bed experiments. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5197687
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
AFTER-HEAT REMOVAL
ALKALI METALS
BREEDER REACTORS
CHALCOGENIDES
COOLING
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
REMOVAL
SIMULATION
SODIUM
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
AFTER-HEAT REMOVAL
ALKALI METALS
BREEDER REACTORS
CHALCOGENIDES
COOLING
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
REMOVAL
SIMULATION
SODIUM
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES