Air—water model studies of cocurrent flow into and along a PWR hot leg to the steam generator

An experimental study is made of the cocurrent flow of air and water at atmospheric pressure from a reactor vessel into and along an approximately ninth-scale replica of the Sizewell ‘B’ PWR hot leg to the steam generator. A flow regime map of conditions in the hot leg is presented. The water interf...

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Published inNuclear engineering and design Vol. 117; no. 3; pp. 251 - 261
Main Author Gardner, G.C.
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.12.1989
Elsevier
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Online AccessGet full text
ISSN0029-5493
1872-759X
DOI10.1016/0029-5493(89)90174-X

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Abstract An experimental study is made of the cocurrent flow of air and water at atmospheric pressure from a reactor vessel into and along an approximately ninth-scale replica of the Sizewell ‘B’ PWR hot leg to the steam generator. A flow regime map of conditions in the hot leg is presented. The water interface level in the reactor vessel as a function of the flowrates is in agreement with a recent theory developed by the author. The same theory predicts the level in the hot leg when discharging two phases through a horizontal break and is in agreement with the results of other workers on this subject for the discharge of air and water up to a pressure of 5 bar and of steam and water up to a pressure of 62 bar. Results on the water level in the hot leg are correlated empirically but, for lower flowrates, the results are in approximate agreement with a theory for the onset of flooding.
AbstractList An experimental study is made of the cocurrent flow of air and water at atmospheric pressure from a reactor vessel into and along an approximately ninth-scale replica of the Sizewell ‘B’ PWR hot leg to the steam generator. A flow regime map of conditions in the hot leg is presented. The water interface level in the reactor vessel as a function of the flowrates is in agreement with a recent theory developed by the author. The same theory predicts the level in the hot leg when discharging two phases through a horizontal break and is in agreement with the results of other workers on this subject for the discharge of air and water up to a pressure of 5 bar and of steam and water up to a pressure of 62 bar. Results on the water level in the hot leg are correlated empirically but, for lower flowrates, the results are in approximate agreement with a theory for the onset of flooding.
Author Gardner, G.C.
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Cites_doi 10.1016/0301-9322(88)90016-X
10.1016/0301-9322(79)90017-X
10.1016/0029-5493(88)90037-4
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Issue 3
Keywords Water
Water level
Hot leg
Model study
Cocurrent flow
Air
Experimental study
Pressurized water reactor
Nuclear reactor
Language English
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Elsevier
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References Gardner (BIB6) 1979; 5
Tuomisto, Kajanto (BIB7) 1988; 107
Smoglie (BIB3) 1984; 3861
Chow (BIB2) 1981
Schrock, Revankar, Mannheimer, Wang (BIB4) 1986
Anderson, Benedetti (BIB5) 1986
Gardner (BIB1) 1988; 14
Gardner (10.1016/0029-5493(89)90174-X_BIB6) 1979; 5
Gardner (10.1016/0029-5493(89)90174-X_BIB1) 1988; 14
Anderson (10.1016/0029-5493(89)90174-X_BIB5) 1986
Schrock (10.1016/0029-5493(89)90174-X_BIB4) 1986
Chow (10.1016/0029-5493(89)90174-X_BIB2) 1981
Smoglie (10.1016/0029-5493(89)90174-X_BIB3) 1984; 3861
Tuomisto (10.1016/0029-5493(89)90174-X_BIB7) 1988; 107
References_xml – volume: 5
  start-page: 201
  year: 1979
  end-page: 209
  ident: BIB6
  article-title: Onset of slugging in horizontal ducts
  publication-title: Int. J. Multiphase Flow
– year: 1986
  ident: BIB4
  article-title: Small break critical discharge — the roles of vapour and liquid entrainment in stratified region upstream of a break
  publication-title: NUREG/CR-4761
– year: 1981
  ident: BIB2
  publication-title: Open Channel Hydraulics
– volume: 107
  start-page: 295
  year: 1988
  end-page: 305
  ident: BIB7
  article-title: Two-phase flow in a full-scale loop seal facility
  publication-title: Nuclear Engrg. Des.
– year: 1986
  ident: BIB5
  article-title: Critical flow through small pipe breaks
  publication-title: EPRI Report NP-4532
– volume: 14
  start-page: 375
  year: 1988
  end-page: 388
  ident: BIB1
  article-title: Cocurrent flow of air and water from a reservoir into a short horizontal pipe
  publication-title: Int. J. Multiphase Flow
– volume: 3861
  year: 1984
  ident: BIB3
  article-title: Two-phase flow through small branches in a horizontal pipe with stratified flow
  publication-title: Kernforschungszentrum Karlsruhe, KfK
– volume: 14
  start-page: 375
  year: 1988
  ident: 10.1016/0029-5493(89)90174-X_BIB1
  article-title: Cocurrent flow of air and water from a reservoir into a short horizontal pipe
  publication-title: Int. J. Multiphase Flow
  doi: 10.1016/0301-9322(88)90016-X
– volume: 5
  start-page: 201
  year: 1979
  ident: 10.1016/0029-5493(89)90174-X_BIB6
  article-title: Onset of slugging in horizontal ducts
  publication-title: Int. J. Multiphase Flow
  doi: 10.1016/0301-9322(79)90017-X
– volume: 107
  start-page: 295
  year: 1988
  ident: 10.1016/0029-5493(89)90174-X_BIB7
  article-title: Two-phase flow in a full-scale loop seal facility
  publication-title: Nuclear Engrg. Des.
  doi: 10.1016/0029-5493(88)90037-4
– year: 1981
  ident: 10.1016/0029-5493(89)90174-X_BIB2
– year: 1986
  ident: 10.1016/0029-5493(89)90174-X_BIB4
  article-title: Small break critical discharge — the roles of vapour and liquid entrainment in stratified region upstream of a break
  publication-title: NUREG/CR-4761
– volume: 3861
  year: 1984
  ident: 10.1016/0029-5493(89)90174-X_BIB3
  article-title: Two-phase flow through small branches in a horizontal pipe with stratified flow
  publication-title: Kernforschungszentrum Karlsruhe, KfK
– year: 1986
  ident: 10.1016/0029-5493(89)90174-X_BIB5
  article-title: Critical flow through small pipe breaks
  publication-title: EPRI Report NP-4532
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StartPage 251
SubjectTerms Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
Title Air—water model studies of cocurrent flow into and along a PWR hot leg to the steam generator
URI https://dx.doi.org/10.1016/0029-5493(89)90174-X
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