Behavior of a failed fuel rod during film boiling operation. [PWR]

Behavior of a failed fuel rod during film boiling operation. [PWR] [electronic resource]

A single rod power-coolant-mismatch test (Test PCM-1) was conducted in the Power Burst Facility to evaluate the behavior of a pressurized water reactor (PWR)-type fuel rod subjected to film boiling operation at high power for a time exceeding that resulting in rod failure. The mechanisms of rod fail...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Idaho National Engineering Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Idaho Falls, Idaho : Oak Ridge, Tenn. : Idaho National Engineering Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
Subjects:
Water Moderated Reactors.
Water Cooled Reactors.
Reactors.
Power-cooling-mismatch Accidents.
Simulation.
Boiling.
Film Boiling.
Pwr Type Reactors.
Pbf Reactor.
Fuel Element Failure.
Accidents.
Phase Transformations.
Pulsed Reactors.
Reactor Accidents.
Tank Type Reactors.
General Studies Of Nuclear Reactors.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:conf-790602-3
E 1.99:conf-790602-3 Available

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