Debris bed studies and experiments at Sandia Laboratories. [LMFBR]
An initial experiment simulating a 58 mm thick LMFBR fuel debris bed has been performed in liquid sodium in which the UO/sub 2/ particles composing the bed were internally heated by nuclear fission. The experiment was performed in the Annular Core Pulse Reactor (ACPR), as part of Sandia Laboratories' program examining the safety of advanced reactors. Supporting research included experiments utilizing other power sources and simulated debris and coolants, analysis and modeling, and auxiliary measurement of material properties and interactions. The specific power attained during the in-reactor experiment ranged up to about 1 kW/kg of UO/sub 2/ while the bulk sodium temperatures ranged up to 838 K. The particle-to-fluid interface does not appear to offer significant resistance to heat transfer at these power levels. The heat transfer behavior of the bed was quite reproducible, and edge effects appeared to be small.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6633471
- Report Number(s):
- NUREG/CR-0263; SAND-78-0299
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-reactor experiments with simulated LMFBR debris beds
Preliminary results from initial in-pile debris bed experiments. [LMFBR]
Postaccident heat removal: debris-bed experiments D-2 and D-3. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7212670
Preliminary results from initial in-pile debris bed experiments. [LMFBR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5197687
Postaccident heat removal: debris-bed experiments D-2 and D-3. [LMFBR]
Technical Report
·
Tue Aug 01 00:00:00 EDT 1978
·
OSTI ID:6494241
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
ALKALI METALS
BREEDER REACTORS
CHALCOGENIDES
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTDOWN
METALS
MOCKUP
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
SODIUM
STRUCTURAL MODELS
TESTING
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
ALKALI METALS
BREEDER REACTORS
CHALCOGENIDES
CORIUM
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTDOWN
METALS
MOCKUP
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
SODIUM
STRUCTURAL MODELS
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES