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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Online Access: |
Online Access |
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Corporate Author: | |
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.
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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. | ||
337 | |a computer |b c |2 rdamedia. | ||
338 | |a online resource |b cr |2 rdacarrier. | ||
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. | |
856 | 4 | 0 | |u http://www.osti.gov/servlets/purl/6168938-PXqfna/ |z Online Access |
907 | |a .b72148214 |b 03-07-23 |c 11-08-12 | ||
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952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:conf-790602-3 |h Superintendent of Documents classification |i web |n 1 |