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FINAL REPORT ON THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.

Technical Report ·
DOI:https://doi.org/10.2172/4018010· OSTI ID:4018010
; ;
Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-25-023342
OSTI ID:
4018010
Report Number(s):
ORNL--4635
Country of Publication:
United States
Language:
English

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FINAL REPORT ON THE SECOND FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY- CLAD FUEL ROD CLUSTER IN TREAT.
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PRELIMINARY EVALUATION OF THE FIRST FUEL ROD FAILURE TRANSIENT TEST OF A ZIRCALOY-CLAD FUEL ROD CLUSTER IN TREAT.
Technical Report · Tue Dec 31 23:00:00 EST 1968 · OSTI ID:4177019
FAILURE MODES OF ZIRCALOY-CLAD FUEL RODS.
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Related Subjects

ACCIDENTS
FAILURES
FUEL CANS
FUEL RODS
LOSS OF COOLANT
N38570* --Research & Test Reactors & Critical Assemblies-- Operation
REACTOR FUEL ELEMENTS/failure of water cooled Zircaloy clad uranium oxide (UO$sub 2$) rod type
effects of coolant loss conditions on
(E)
REACTOR SAFETY EXPERIMENTS/fuel elements in TREAT
effects of coolant loss conditions on failure of Zircaloy clad uranium oxide (UO$sub 2$) rod type
(E)
REACTORS
WATER-COOLED/coolant loss accident conditions in
analysis of fuel rod failure for
(E)
REACTORS
WATER-COOLED/fuel elements for
effects of coolant loss conditions on failure of Zircaloy clad uranium oxide (UO$sub 2$) rod type
(E)
TESTING
TRANSIENTS
TREAT
URANIUM DIOXIDE
WATER COOLED REACTORS
ZIRCALOY