Experiment data report for Multirod Burst Test (MRBT) bundle B-6. [PWR; BWR]

Technical Report · Sun Jul 01 04:00:00 EDT 1984

DOI:https://doi.org/10.2172/6503742· OSTI ID:6503742

Chapman, R H; Longest, A W; Crowley, J L

A reference source of MRBT bundle B-6 test data is presented with minimum interpretation. The primary objective of this 8 x 8 multirod burst test was to investigate cladding deformation in the alpha-plus-beta-Zircaloy temperature range under simulated light-water-reactor (LWR) loss-of-coolant accident (LOCA) conditions. B-6 test conditions simulated the adiabatic heatup (reheat) phase of an LOCA and produced very uniform temperature distributions. The fuel pin simulators were electrically heated (average linear power generation of 1.42 kW/m) and were slightly cooled with a very low flow (Re approx. 140) of low-pressure superheated steam. The cladding temperature increased from the initial temperature (330/sup 0/C) to the burst temperature at a rate of 3.5/sup 0/C/s. The simulators burst in a very narrow temperature range, with an average of 930/sup 0/C. Cladding burst strain ranged from 21 to 56%, with an average of 31%. Volumetric expansion over the heated length of the cladding ranged from 16 to 32%, with an average of 23%. 23 references.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6503742
• Report Number(s): NUREG/CR-3460; ORNL/TM-8890; ON: TI84015734
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALLOYS
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DATA
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FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
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LOSS OF COOLANT
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRAINS
STRESSES
TEMPERATURE DISTRIBUTION
TEMPERATURE GRADIENTS
TEST FACILITIES
THERMAL STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS