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150804e19840101||| ot f0|||||eng|d |
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|a (TOE)ost5444667
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|a (TOE)5444667
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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 21
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|a E 1.99:nureg/cr-3577
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|a E 1.99:nureg/cr-3577
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| 088 |
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|a nureg/cr-3577
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| 245 |
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|a Measurement of countercurrent phase separation and distribution in a two-dimensional test section
|h [electronic resource]
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| 260 |
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|a Troy, N.Y. :
|b Rensselaer Polytechnic Institute. Department of Nuclear Engineering ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1984.
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| 300 |
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|a Pages: 221 :
|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 SciTech Connect.
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| 500 |
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|a 01/01/1984.
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| 500 |
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|a "nureg/cr-3577"
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| 500 |
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|a "DE84900662"
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| 500 |
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|a Bukhari, K M; Lahey, Jr, R T.
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| 520 |
3 |
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|a The degree of phase separation that occurs in the core of a pressurized water reactor (PWR) during various postulated accidents is an important consideration for studying the course of events during such accidents. The dependence of countercurrent phase separation and distribution phenomena on flow quality, mass flux and system geometry was studied experimentally in a two-dimensional (2-D) test section. A two-phase (air/water) mixture flowed upwards and single-phase water flowed downward along one side of the test section. This countercurrent flow configuration was intended to simulate the so-called chimney effect in the diabatic JAERI 2-D experiments in Japan. A large air/water loop used with a 91.44 cm x 91.44 cm x 1.27 cm test section to study phase separation and distribution effects. A traversing single beam gamma-densitometer was used to measure the chordal average void fractions at several elevations along the test section. Cross-plots between various flow conditions and geometries were made. An error analysis giving the total error in the void fraction measurements was also performed. High speed photographs were also made of the flow structure, to provide information on flow regimes. The photographic records and the void fraction and hydraulic inflow/outflow data are presented in a form suitable for the assessment of advanced generation computer codes (e.g., TRAC)
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| 650 |
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|a Loss Of Coolant.
|2 local.
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| 650 |
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|a Two-Phase Flow.
|2 local.
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| 650 |
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7 |
|a Pwr Type Reactors.
|2 local.
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| 650 |
|
7 |
|a Air.
|2 local.
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| 650 |
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|a Coolant Loops.
|2 local.
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| 650 |
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|a Counter Current.
|2 local.
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| 650 |
|
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|a Reactor Accidents.
|2 local.
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| 650 |
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|a Simulation.
|2 local.
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| 650 |
|
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|a Void Fraction.
|2 local.
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| 650 |
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|a Water.
|2 local.
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| 650 |
|
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|a Accidents.
|2 local.
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| 650 |
|
7 |
|a Cooling Systems.
|2 local.
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| 650 |
|
7 |
|a Energy Systems.
|2 local.
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| 650 |
|
7 |
|a Fluid Flow.
|2 local.
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| 650 |
|
7 |
|a Fluids.
|2 local.
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| 650 |
|
7 |
|a Gases.
|2 local.
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| 650 |
|
7 |
|a Hydrogen Compounds.
|2 local.
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| 650 |
|
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|a Oxygen Compounds.
|2 local.
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| 650 |
|
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|a Reactors.
|2 local.
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| 650 |
|
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|a Water Cooled Reactors.
|2 local.
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| 650 |
|
7 |
|a Water Moderated Reactors.
|2 local.
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| 650 |
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|a General Studies Of Nuclear Reactors.
|2 edbsc.
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| 650 |
|
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|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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| 700 |
1 |
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|a Bukhari, K M
|4 aut.
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| 700 |
1 |
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|a Lahey, Jr, R T
|4 aut.
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| 710 |
2 |
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|a Rensselaer Polytechnic Institute.
|b Department of Nuclear Engineering.
|4 res.
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| 710 |
1 |
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|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/5444667/
|z Online Access
|
| 907 |
|
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|a .b80946100
|b 03-08-23
|c 08-04-15
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| 998 |
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|a web
|b 08-04-15
|c f
|d m
|e p
|f eng
|g
|h 0
|i 1
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| 956 |
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|a Information bridge
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| 999 |
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|i 015e9f80-5bbe-5cc8-bafc-fa0517fc5509
|s f9459e4d-078a-54a4-992b-3306046fc910
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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:nureg/cr-3577
|h Superintendent of Documents classification
|i web
|n 1
|
