Use of radiography to monitor structural movement in GCFR-CFTL fuel rod bundles [electronic resource]
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...
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| Online Access: |
Online Access (via OSTI) |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1979.
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| Subjects: |
| Summary: | 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. |
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| Item Description: | Published through SciTech Connect. 12/01/1979. "ornl/tm-7050" Batey, J.M. |
| Physical Description: | Pages: 60 : digital, PDF file. |