FINAL REPORT ON THE SECOND FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-26-016895
- OSTI ID:
- 4691610
- Report Number(s):
- ORNL--4710
- Country of Publication:
- United States
- Language:
- English
Similar Records
FINAL REPORT ON THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.
PRELIMINARY EVALUATION OF THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY-CLAD FUEL ROD CLUSTER IN TREAT.
FAILURE MODES OF ZIRCALOY-CLAD FUEL RODS.
Technical Report
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Thu Dec 31 23:00:00 EST 1970
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OSTI ID:4018010
PRELIMINARY EVALUATION OF THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY-CLAD FUEL ROD CLUSTER IN TREAT.
Technical Report
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Tue Dec 31 23:00:00 EST 1968
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OSTI ID:4177019
FAILURE MODES OF ZIRCALOY-CLAD FUEL RODS.
Technical Report
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Sun Dec 31 23:00:00 EST 1967
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OSTI ID:4494557
Related Subjects
FAILURES
FISSION PRODUCTS
FISSION PRODUCTS/release from failed Zircaloy clad uranium oxide (UO$sub 2$) fuel rods
(E)
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
N78150* --Power Reactor Development--Fuel Systems & Components
REACTOR FUEL ELEMENTS/ failure characteristics of water cooled Zircaloy clad uranium oxide (UO$sub 2$) rod type
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REACTOR SAFETY EXPERIMENTS/fuel element failure characteristics in TREAT
simulated coolant loss accident for Zircaloy clad uranium oxide (UO$sub 2$)
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REACTORS
WATER-COOLED/ fuel elements of
coolant loss accident failure characteristics of Zircaloy clad uranium oxide (UO$sub 2$) rod type
(E)
TESTING
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/failure of Zircaloy clad fuel elements of
characteristics of coolant loss accident
WATER COOLED REACTORS
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FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
N78150* --Power Reactor Development--Fuel Systems & Components
REACTOR FUEL ELEMENTS/ failure characteristics of water cooled Zircaloy clad uranium oxide (UO$sub 2$) rod type
coolant loss accident
(E)
REACTOR SAFETY EXPERIMENTS/fuel element failure characteristics in TREAT
simulated coolant loss accident for Zircaloy clad uranium oxide (UO$sub 2$)
(E)
REACTORS
WATER-COOLED/ fuel elements of
coolant loss accident failure characteristics of Zircaloy clad uranium oxide (UO$sub 2$) rod type
(E)
TESTING
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/failure of Zircaloy clad fuel elements of
characteristics of coolant loss accident
WATER COOLED REACTORS
ZIRCALOY