Use of radiography to monitor structural movement in GCFR-CFTL fuel rod bundles

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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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
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.
Subjects:
Gcfr Reactor.
Fuel Motion Detection.
Loss Of Coolant.
Fuel Rods.
Industrial Radiography.
Reactor Safety.
Simulation.
Test Facilities.
Accidents.
Breeder Reactors.
Detection.
Epithermal Reactors.
Fast Reactors.
Fbr Type Reactors.
Fuel Elements.
Gas Cooled Reactors.
Gcfr Type Reactors.
Helium Cooled Reactors.
Materials Testing.
Nondestructive Testing.
Reactor Accidents.
Reactor Components.
Reactors.
Safety.
Testing.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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