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|a (TOE)ost5058818
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|a (TOE)5058818
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|a TOE
|c TOE
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:ornl/nureg/tm-180
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| 086 |
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|a E 1.99:ornl/nureg/tm-180
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| 088 |
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|a ornl/nureg/tm-180
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| 245 |
0 |
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|a Critical heat flux experimentation in an annular test section. [PWR]
|h [electronic resource]
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| 260 |
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|a Oak Ridge, Tenn. :
|b Oak Ridge National Laboratory. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1978.
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| 300 |
|
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|a Pages: 32 :
|b digital, PDF file.
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| 336 |
|
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|a text
|b txt
|2 rdacontent.
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| 337 |
|
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 03/07/1978.
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| 500 |
|
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|a "ornl/nureg/tm-180"
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| 500 |
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|a White, J.D.; Levin, A.E.
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| 520 |
3 |
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|a Steady-state critical heat flux experiments have been performed in the Forced Convection Test Facility (FCTF), an annular test section containing a single electrically heated rod, for the purpose of testing the applicability of existing critical heat flux correlations. Good accuracy has been obtained using the MacBeth-Barnett critical heat flux correlation for annuli, corrected for the ''stepped cosine'' power profile of the heater. The equivalent diameter of the test section, based on the wetted perimeter, is 2.1 cm (0.83 in.); the heated-to-wetted-perimeter ratio is 0.252. The heated length of the heater rod is 366 cm (144 in.). Nominal pressures for the tests have ranged from 7.2 to 15.5 MN/m² (1044 to 2250 psia); coolant flow rates have been 0.32 dm³/sec (5 gpm), 0.63 dm³/sec (10 gpm), and 1.26 dm³/sec (20 gpm); and heater powers of 72 kW, 122 kW, and 144 kW have been used. Maximum error in prediction of first observed critical heat flux is 21 percent; rms error is 11.7 percent. Attempts have also been made to predict the occurrence of critical heat flux during blowdowns (depressurization transients) of the FCTF. The results of these predictions are inconclusive at this time.
|
| 536 |
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|b W-7405-ENG-26.
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| 650 |
|
7 |
|a Water Moderated Reactors.
|2 local.
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| 650 |
|
7 |
|a Water Cooled Reactors.
|2 local.
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| 650 |
|
7 |
|a Reactors.
|2 local.
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| 650 |
|
7 |
|a Structural Models.
|2 local.
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| 650 |
|
7 |
|a Critical Heat Flux.
|2 local.
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| 650 |
|
7 |
|a Departure Nucleate Boiling.
|2 local.
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| 650 |
|
7 |
|a Nucleate Boiling.
|2 local.
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| 650 |
|
7 |
|a Simulation.
|2 local.
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| 650 |
|
7 |
|a Boiling.
|2 local.
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| 650 |
|
7 |
|a Heat Transfer.
|2 local.
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| 650 |
|
7 |
|a Mockup.
|2 local.
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| 650 |
|
7 |
|a Test Facilities.
|2 local.
|
| 650 |
|
7 |
|a Energy Transfer.
|2 local.
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| 650 |
|
7 |
|a Heat Flux.
|2 local.
|
| 650 |
|
7 |
|a Transients.
|2 local.
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| 650 |
|
7 |
|a Blowdown.
|2 local.
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| 650 |
|
7 |
|a Pwr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Phase Transformations.
|2 local.
|
| 650 |
|
7 |
|a Engineering.
|2 edbsc.
|
| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
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| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
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|a Oak Ridge National 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/5058818-nNuwLe/
|z Online Access
|
| 907 |
|
|
|a .b72077293
|b 03-07-23
|c 11-08-12
|
| 998 |
|
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|a web
|b 11-08-12
|c f
|d m
|e p
|f eng
|g tnu
|h 0
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
f |
|i 9123c912-9480-57c2-9e50-f51110685ab7
|s 53b7f9d7-bdd4-5a12-b546-5e660c65c779
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/nureg/tm-180
|h Superintendent of Documents classification
|i web
|n 1
|
