Use of radiography to monitor structural movement in GCFR-CFTL fuel rod bundles
The Core Flow Test Loop (CFTL) is designed to simulate accident conditions of the Gas-Cooled Fast Reactor (GCFR). The reactor fuel rods are simulated by electric heater rods. An important consideration in data acquisition for loss of coolant studies is structural movement in the test bundle, that is, axial expansion and laterial movement (bowing) of fuel rod simulators and ducts. Radiography is superior to proximity sensors and extensometers for monitoring structural movement because radiography is external to the CFTL vessel and nonintrusive. Both fluoroscopy and film radiography were investigated. Both techniques were determined feasible, and both are recommended for GCFR-CFTL applications.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5715471
- Report Number(s):
- ORNL/TM-7050
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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REACTOR SAFETY
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