Experiment data report for Multirod Burst Test (MRBT) bundle B-4. [PWR; BWR]

Conference · Wed Dec 01 00:00:00 EST 1982

OSTI ID:6669114

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

A compilation of bundle B-4 test data is presented. These data were obtained during the test and from pretest and posttest examination of the test array. They are presented in considerable detail but with minimum interpretation. The B-4 test is the only 6 x 6 array in a series of 4 x 4, 6 x 6, and 8 x 8 bundle tests performed by the Multirod Burst Test Program at Oak Ridge National Laboratory. This research is sponsored by the Nuclear Regulatory Commission and is designed to investigate Zircaloy cladding deformation behavior under simulated light-water-reactor loss-of-coolant accident conditions. A brief description of the experiment and a summary of the test results are included with the detailed results of the B-4 test. Both graphical and tabular formats are used to show temperature and pressure data as functions of test time and strain data for the cladding in each of the fuel rod simulators. Photographic documentation is provided for both the overall bundle, before and after testing, and the 36 tubes as they were removed from the tested bundle for strain measurements.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6669114
• Report Number(s): NUREG/CR-2968; ORNL/TM-8509; ON: DE83003985
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CANS
FUEL RODS
LOSS OF COOLANT
DEFORMATION
THERMAL STRESSES
HEAT TRANSFER
HYDRAULICS
TEST FACILITIES
PWR TYPE REACTORS
EXPERIMENTAL DATA
FUEL ASSEMBLIES
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ZIRCALOY
ACCIDENTS
ALLOYS
DATA
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled