PRELIMINARY EVALUATION OF THE FIRST 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-24-018688
- OSTI ID:
- 4177019
- Report Number(s):
- ORNL-TM--2774
- Country of Publication:
- United States
- Language:
- English
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FINAL REPORT ON THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.
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Thu Dec 31 23:00:00 EST 1970
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OSTI ID:4018010
FINAL REPORT ON THE SECOND FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.
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Fri Dec 31 23:00:00 EST 1971
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Related Subjects
FAILURES
FUEL CANS
FUEL ELEMENTS
LOSSES
N38180* --Power Reactor Development--Safety & Siting
REACTOR FUEL ELEMENTS/failure of Zircaloy clad uranium oxide (UO$sub 2$)
during water coolant loss accidents
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS/fuel element failure transient testing in TREAT
evaluation of irradiated Zircaloy clad
REACTORS
WATER-COOLED/ fuel elements for
failure transient testing of Zircaloy clad
RESEARCH REACTORS
TRANSIENTS
TREAT
URANIUM DIOXIDE
WATER COOLANT
WATER COOLED REACTORS
ZIRCALOY
FUEL CANS
FUEL ELEMENTS
LOSSES
N38180* --Power Reactor Development--Safety & Siting
REACTOR FUEL ELEMENTS/failure of Zircaloy clad uranium oxide (UO$sub 2$)
during water coolant loss accidents
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS/fuel element failure transient testing in TREAT
evaluation of irradiated Zircaloy clad
REACTORS
WATER-COOLED/ fuel elements for
failure transient testing of Zircaloy clad
RESEARCH REACTORS
TRANSIENTS
TREAT
URANIUM DIOXIDE
WATER COOLANT
WATER COOLED REACTORS
ZIRCALOY