TREAT F-series LMFBR loss-of-flow experiments
Conference
·
OSTI ID:6210858
The F-series tests are done to study fuel behavior in an LMFBR LOF accident. These tests are performed in dry (no sodium) capsules to separate out effects of sodium on fuel behavior and, in F3 and subsequent tests, to permit visual observation. Justification for a dry capsule is that the fuel behavior of interest such as fuel-pin breakup and extensive axial motion are assumed to occur after sodium voiding in a LOF accident. Two distinct F-series designs have been subject to TREAT tests. The design used for tests F1 and F2 permitted a study of extensive axial fuel motion and used the fast neutron hodoscope as the principal instrumentation. The second design, used for tests F3 and F4 and to e used for tests F5 and F6, permits a study of fuel pin break-up with high speed photography as the principal instrumentation.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6210858
- Report Number(s):
- CONF-820406-31; ON: DE83008943
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
TEST FACILITIES
TEST REACTORS
THERMAL REACTORS
TREAT REACTOR
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
TEST FACILITIES
TEST REACTORS
THERMAL REACTORS
TREAT REACTOR