Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
Conference
·
OSTI ID:6880789
- Argonne National Lab., IL (United States)
This report discusses three furnace heating tests which were conducted with irradiated, HT9-clad and U-19wt.%Pu-l0wt.%Zr-alloy fuel, Mk-V-type fuel elements in the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory, Illinois. In general, very significant safety margins for fuel-element cladding breaching have been demonstrated in these tests, under conditions that would envelop a bounding unlikely loss-of-flow event in EBR-II. Highlights of the test results will be given, as well as discussions of the cladding breaching mechanisms, axial fuel motion, and fuel surface liquefaction found in high-temperature testing of irradiated metallic fuel elements.
- Research Organization:
- Argonne National Lab., IL (United States). Materials and Components Technology Div.
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6880789
- Report Number(s):
- ANL/MCT/CP-76404; CONF-921102--31; ON: DE93002908
- Country of Publication:
- United States
- Language:
- English
Similar Records
Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
Fuel/cladding compatibility in low-burnup U-26Pu-10Zr/HT9 fuel at elevated temperatures
Conference
·
Sat Oct 31 23:00:00 EST 1992
·
OSTI ID:10104888
Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6680965
Fuel/cladding compatibility in low-burnup U-26Pu-10Zr/HT9 fuel at elevated temperatures
Technical Report
·
Sun Sep 01 00:00:00 EDT 1991
·
OSTI ID:714936
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
ALLOY-HT-9
ALLOYS
ANL
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MARTENSITIC STEELS
MATERIALS
MOLYBDEN
MOLYBDENUM ADDITIONS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RUPTURES
SAFETY
SODIUM COOLED REACTORS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
ALLOY-HT-9
ALLOYS
ANL
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MARTENSITIC STEELS
MATERIALS
MOLYBDEN
MOLYBDENUM ADDITIONS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RUPTURES
SAFETY
SODIUM COOLED REACTORS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS