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:

MARC

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245 0 0 |a Behavior of a failed fuel rod during film boiling operation. [PWR]  |h [electronic resource] 
260 |a Idaho Falls, Idaho :  |b Idaho National Engineering Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 1979. 
300 |a Pages: 4 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
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500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 01/01/1979. 
500 |a "conf-790602-3" 
500 |a ANS annual meeting, Atlanta, GA, USA, 3 Jun 1979. 
500 |a Cook, B.A.; Sparks, D.T.; Hobbins, R.R. 
520 3 |a 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 failure, the test rod response following failure, and the consequences of operation with a large molten fuel radius following fuel rod failure were investigated through destructive and nondestructive examination. 
536 |b EY-76-C-07-1570. 
650 7 |a Water Moderated Reactors.  |2 local. 
650 7 |a Water Cooled Reactors.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Power-cooling-mismatch Accidents.  |2 local. 
650 7 |a Simulation.  |2 local. 
650 7 |a Boiling.  |2 local. 
650 7 |a Film Boiling.  |2 local. 
650 7 |a Pwr Type Reactors.  |2 local. 
650 7 |a Pbf Reactor.  |2 local. 
650 7 |a Fuel Element Failure.  |2 local. 
650 7 |a Accidents.  |2 local. 
650 7 |a Phase Transformations.  |2 local. 
650 7 |a Pulsed Reactors.  |2 local. 
650 7 |a Reactor Accidents.  |2 local. 
650 7 |a Tank Type Reactors.  |2 local. 
650 7 |a General Studies Of Nuclear Reactors.  |2 edbsc. 
650 7 |a Specific Nuclear Reactors And Associated Plants.  |2 edbsc. 
710 2 |a Idaho National Engineering Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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