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
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Related Subjects
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ACCIDENTS
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
DEFORMATION
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PBF REACTOR
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TANK TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS