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Evaluation of the thermal-hydraulic and fuel rod thermal and mechanical deformation behavior during the first Power Burst Facility nuclear blowdown tests

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5944329
A preliminary evaluation was made of the results from the LOC-11 nuclar blowdown tests conducted in the Power Burst Facility. The objective of the LOC-11 tests was to measure the thermal and mechanical deformation behavior of pressurized and unpressurized fuel rods exposed to a blowdown (coolant depressurization) similar to that expected in a pressurized water reactor (PWR) during a hypothesized double-ended cold-leg break. Incipient fuel rod cladding collapse and swelling occurred during Test LOC-11C, when the two unpressurized and two pressurized PWR-type rods were exposed to a system blowdown with measured cladding temperatures increasing to 1030 K. To better understand the test results and to evaluate prediction capability, RELAP4-calculated coolant thermal-hydraulic and fuel rod thermal behavior and FRAP-T4-calculated fuel rod mechanical deformation behavior were compared with the test LOC-11C data. The RELAP4 posttest calculations of coolant behavior generally agreed well with the measured coolant behavior; however, the calculated cladding surface temperatures were approx. 50 K greater than measured. The FRAP-T4 calculations of cladding deformation using best-estimate models slightly overpredicted the observed ballooning of the pressurized rods and underpredicted the collapse of the unpressurized rods.
Research Organization:
EG and G Idaho, Inc., Idaho Falls
OSTI ID:
5944329
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 44:3; ISSN NUTYB
Country of Publication:
United States
Language:
English