Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow (English)
- New search for: Chenu, A.
- New search for: Mikityuk, K.
- New search for: Chawla, R.
- New search for: Chenu, A.
- New search for: Mikityuk, K.
- New search for: Chawla, R.
In:
NUCLEAR ENGINEERING AND DESIGN
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241
, 9
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3898-3909
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2011
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ISSN:
- Article (Journal) / Print
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Title:Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow
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Contributors:
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Published in:NUCLEAR ENGINEERING AND DESIGN ; 241, 9 ; 3898-3909
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Publisher:
- New search for: Elsevier Science B.V., Amsterdam.
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Publication date:2011-01-01
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Size:12 pages
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ISSN:
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Type of media:Article (Journal)
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Type of material:Print
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Language:English
- New search for: 621.48
- Further information on Dewey Decimal Classification
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Classification:
DDC: 621.48 -
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© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents – Volume 241, Issue 9
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 3375
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ForewordHugon, Michel / Hassan, Yassin et al. | 2011
- 3376
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FISA-2009 Conference on Euratom Research and Training Activities: Nuclear Fission – Past, Present and Future (Generation-II, -III and -IV+Partitioning and Transmutation)Bhatnagar, V. / Deffrennes, M. / Hugon, M. / Manolatos, P. / Ptackova, K. / Van Goethem, G. / Webster, S. et al. | 2011
- 3389
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Plant life management and modernisation: Research challenges in the EURintamaa, R. / Aho-Mantila, I. et al. | 2010
- 3395
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Nuclear and Radiological Emergency Management and Rehabilitation Strategies: Towards a EU approach for decision support toolsRaskob, W. / Gering, F. / Lochard, J. / Nisbet, A. / Starostova, V. / Tomic, B. et al. | 2010
- 3403
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PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen plant lifetimeAl Mazouzi, A. / Alamo, A. / Lidbury, D. / Moinereau, D. / Van Dyck, S. et al. | 2011
- 3416
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NURESIM – A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysisChauliac, Christian / Aragonés, José-Maria / Bestion, Dominique / Cacuci, Dan Gabriel / Crouzet, Nicolas / Weiss, Frank-Peter / Zimmermann, Martin A. et al. | 2010
- 3427
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ACSEPT—Partitioning technologies and actinide science: Towards pilot facilities in EuropeBourg, S. / Hill, C. / Caravaca, C. / Rhodes, C. / Ekberg, C. / Taylor, R. / Geist, A. / Modolo, G. / Cassayre, L. / Malmbeck, R. et al. | 2011
- 3436
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Impact of partitioning and transmutation on the high level waste managementGonzález-Romero, E.M. et al. | 2011
- 3445
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Meeting EU's energy needs through nuclear fission: Synergy of public and private research in an international contextBamberger, Yves / Hutin, Jean-Pierre / Delbecq, Jean-Michel et al. | 2010
- 3451
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Sustainable integration of EU research in severe accident phenomenology and managementVan Dorsselaere, Jean-Pierre / Albiol, Thierry / Chaumont, Bernard / Haste, Tim / Journeau, Christophe / Meyer, Leonhard / Sehgal, Bal Raj / Schwinges, Bernd / Beraha, David / Annunziato, Alessandro et al. | 2011
- 3461
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European Commission – 7th Framework ProgrammeFiorini, G.L. / Vasile, A. et al. | 2011
- 3470
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European lead fast reactor—ELSYAlemberti, Alessandro / Carlsson, Johan / Malambu, Edouard / Orden, Alfredo / Struwe, Dankward / Agostini, Pietro / Monti, Stefano et al. | 2011
- 3481
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Gas cooled fast reactor research in EuropeStainsby, Richard / Peers, Karen / Mitchell, Colin / Poette, Christian / Mikityuk, Konstantin / Somers, Joe et al. | 2011
- 3490
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High and very high temperature reactor research for multipurpose energy applicationsHittner, Dominique / Bogusch, Edgar / Fütterer, Michael / de Groot, Sander / Ruer, Jacques et al. | 2011
- 3505
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European supercritical water cooled reactorSchulenberg, T. / Starflinger, J. / Marsault, P. / Bittermann, D. / Maráczy, C. / Laurien, E. / Lycklama à Nijeholt, J.A. / Anglart, H. / Andreani, M. / Ruzickova, M. et al. | 2010
- 3514
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Innovative materials for Gen IV systems and transmutation facilities: The cross-cutting research project GETMATFazio, Concetta / Briceno, Dolores Gomez / Rieth, Michael / Gessi, Alessandro / Henry, Jean / Malerba, Lorenzo et al. | 2010
- 3521
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Basic research in support of innovative fuels design for the GEn IV systems: The F-BRIDGE projectValot, Carole / Bertolus, Marjorie / Konings, Rudy / Somers, Joe / de Groot, Sander et al. | 2011
- 3530
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ENEN's approaches and initiatives for nuclear education and trainingSafieh, Joseph / De Regge, Peter / Kusumi, Ryoko et al. | 2010
- 3540
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Integrated infrastructure initiatives for material testing reactor innovationsDekeyser, Jean / Vermeeren, Ludo / Iracane, Daniel et al. | 2011
- 3553
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Large eddy simulation of turbulent flow surrounding two simulated CANDU fuel bundlesZhang, X. / Yu, S.D. et al. | 2011
- 3573
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Effect of notch dimension on the fatigue life of V-notched structureChang-zheng, Cheng / Naman, Recho / Zhong-rong, Niu / Huan-lin, Zhou et al. | 2011
- 3580
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Probabilistic assessment of creep crack growth rate for Gr. 91 steelKim, Woo-Gon / Park, Jae-Young / Hong, Sung-Deok / Kim, Seon-Jin et al. | 2011
- 3587
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Optimized aspect ratios of restrained thick-wall cylinders by virtue of Poisson's ratio selection. Part two: Temperature applicationWhitty, J.P.M. / Henderson, B. / Francis, J. et al. | 2011
- 3596
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Determination of fatigue curve parameters at cyclic strain limited loading according to the mechanical characteristics of power energy structural materialsBražėnas, Algis / Vaičiulis, Dainius et al. | 2011
- 3605
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Extending image processing strain measurement system to evaluate fracture behavior of wall-thinned pipesTsuji, Masataka / Meshii, Toshiyuki et al. | 2011
- 3613
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Transient thermal stress intensity factors for Mode I edge-cracksZhou, Zhen-huan / Xu, Xin-sheng / Leung, Andrew Yee-tak / Guan, Zhen-qun et al. | 2011
- 3624
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Influence of pump starting times on transient flows in pipesElaoud, Sami / Hadj-Taïeb, Ezzeddine et al. | 2011
- 3632
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Buckling assessment procedure for large diameter vessel with multiple local thin areas subjected to external momentMukaimachi, Norihiko / Konosu, Shinji et al. | 2011
- 3645
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Verification and validation of a CFD model for simulations of large-scale compartment firesSuard, S. / Lapuerta, C. / Babik, F. / Rigollet, L. et al. | 2011
- 3658
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A review on the clad failure studiesAlam, Tanweer / Khan, Mohd. Kaleem / Pathak, Manabendra / Ravi, K. / Singh, Ritu / Gupta, S.K. et al. | 2011
- 3678
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Calculation of heat capacity of the nuclear fuels UO2 and NpO2 using integer and non-integer n-dimensional Debye functionsKoç, H. / Eser, E. / Mamedov, B.A. et al. | 2011
- 3683
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CFD applications in the Pebble Bed Modular Reactor Project: A decade of progressJanse van Rensburg, J.J. / Kleingeld, M. et al. | 2011
- 3697
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Uncertainty and sensitivity analyses as a validation tool for BWR bundle thermal–hydraulic predictionsHernandez-Solis, Augusto / Ekberg, Christian / Demaziere, Christophe / Jensen, Arvid Ödegård / Bredolt, Ulf et al. | 2011
- 3707
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An integrated expert system for optimum in core fuel managementElmoatty, Mona S. Abd / Nagy, M.S. / Aly, Mohamed N. / Shaat, M.K. et al. | 2011
- 3719
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Evolution in the design and development of the in-service inspection device for the Indian 500MWe Fast Breeder ReactorSingh, Ashutosh Pratap / Rajagopalan, C. / Rakesh, V. / Rajendran, S. / Venugopal, S. / Kasiviswanathan, K.V. / Jayakumar, T. et al. | 2011
- 3729
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BWR fuel cycle optimization using neural networksOrtiz-Servin, Juan José / Castillo, José Alejandro / Pelta, David Alejandro et al. | 2011
- 3736
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Characterization of radiation fields and dose assessment from fuels manufacturing for advanced fuel cyclesHawkins, Benjamin J. / Knight, Travis W. et al. | 2011
- 3748
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Nondestructive measurement of the weight of kernels in a simulated cylindrical fuel compact for HTGR using X-ray computed tomographyKim, Woong Ki / Lee, Young Woo / Cho, Moon Sung et al. | 2011
- 3753
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A fuel performance analysis for a 450MWth deep burn-high temperature reactorKim, Young Min / Jo, Chang Keun / Jun, Ji Su / Cho, Moon Sung / Venneri, Francesco et al. | 2011
- 3761
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Wave propagation visualization in an experimental model for a control rod drive mechanism assemblyLee, Jung-Ryul / Jeong, Hyomi / Kong, Churl-Won et al. | 2011
- 3768
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The reactor physics characteristics of a transuranic mixed oxide fuel in a heavy water moderated reactorMorreale, A.C. / Garland, W.J. / Novog, D.R. et al. | 2011
- 3777
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Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore systemKotlyar, D. / Shaposhnik, Y. / Fridman, E. / Shwageraus, E. et al. | 2011
- 3787
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Study of nitrogen injection to enhance forced convection for gas fast reactorsTauveron, N. / Dor, I. / Bentivoglio, F. et al. | 2011
- 3804
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A containment analysis for SBLOCA in the refurbished Wolsong-1 Nuclear Power PlantKim, Tech-Mo / Park, Jong-Ho et al. | 2011
- 3812
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Parametric analyses of partial sub-assembly blockages of the 50MWth gas cooled experimental technology and demonstrator reactor (ETDR)Carlsson, J. / Paffumi, E. et al. | 2011
- 3824
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Modeling pressure suppression pool hydrodynamics in the ABWR containmentSawant, Pravin / Khatib-Rahbar, Mohsen et al. | 2011
- 3839
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PATH – An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal HydraulicsGnanadhas, Lydia / Sharma, Anil Kumar / Malarvizhi, B. / Murthy, S.S. / Hemanth Rao, E. / Kumaresan, M. / Ramesh, S.S. / Harvey, J. / Nashine, B.K. / Chellapandi, P. et al. | 2011
- 3851
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CFD for subcooled flow boiling: Simulation of DEBORA experimentsKrepper, Eckhard / Rzehak, Roland et al. | 2011
- 3867
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Thermal-fluid characteristics of the transuranics fuel in a deep-burn HTR coreJun, Ji Su / Lim, Hong Sik / Jo, Chang Keun / Noh, Jae Man / Venneri, Francesco et al. | 2011
- 3879
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Sensitivity analysis of numerically determined linear stability boundaries of a supercritical heated channelT’Joen, C. / Gilli, L. / Rohde, M. et al. | 2011
- 3890
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A droplet entrainment model based on the force balance of an interfacial wave in two-phase annular flowRyu, Seok-Hee / Park, Goon-Cherl et al. | 2011
- 3898
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Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flowChenu, A. / Mikityuk, K. / Chawla, R. et al. | 2011
- 3910
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Design of the advanced accumulator for the pressurized water reactorShiraishi, Tadashi et al. | 2011
- 3925
-
Passive containment cooling system (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a postulated Loss of Coolant Accident (LOCA)Paladino, Domenico / Dreier, Joerg et al. | 2011
- 3935
-
Experimental investigation of spray induced gas stratification break-up and mixing in two interconnected vesselsErkan, Nejdet / Kapulla, Ralf / Mignot, Guillaume / Zboray, Robert / Paladino, Domenico et al. | 2011
- 3945
-
Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithmCong, Tenglong / Chen, Ronghua / Su, Guanghui / Qiu, Suizheng / Tian, Wenxi et al. | 2011
- 3952
-
Prediction of void fraction for PWR and BWR conditions with the sub-channel code F-COBRA-TFGabriel, H. / Glück, M. et al. | 2011
- 3967
-
Fuzzy methodology applied to Probabilistic Safety Assessment for digital system in nuclear power plantsGuimarães, Antonio César Ferreira / Lapa, Celso Marcelo Franklin / Moreira, Maria de Lourdes et al. | 2011
- 3977
-
Severe accident management strategy verification for VVER-1000 (V320) reactorChatterjee, B. / Mukhopadhyay, D. / Lele, H.G. / Atanasova, B. / Groudev, Pavlin et al. | 2011
- 3985
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A probabilistic seismic risk assessment procedure for nuclear power plants: (II) ApplicationHuang, Yin-Nan / Whittaker, Andrew S. / Luco, Nicolas et al. | 2011
- 3996
-
A probabilistic seismic risk assessment procedure for nuclear power plants: (I) MethodologyHuang, Yin-Nan / Whittaker, Andrew S. / Luco, Nicolas et al. | 2011
- 4004
-
Failure analysis of the standby liquid control system for a boiling water reactor with fuzzy cognitive mapsNúñez-Carrera, Alejandro / Espinosa-Paredes, Gilberto / Cruz-Esteban, Hugo et al. | 2011
- 4013
-
Knowledge-directed characterization of nuclear power plant reactor core parametersWest, Graeme M. / McArthur, Stephen D.J. / Towle, Dave et al. | 2011
- 4026
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PARIS project: Radiolytic oxidation of molecular iodine in containment during a nuclear reactor severe accident: Part 2. Formation and destruction of iodine oxides compounds under irradiation – Experimental results modellingBosland, L. / Funke, F. / Langrock, G. / Girault, N. et al. | 2011
- 4045
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Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channelsGang, Wu / Bi, Qincheng / Yang, Zhendong / Wang, Han / Zhu, Xiaojing / Hao, Hou / Leung, L.K.H. et al. | 2011
- 4055
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New explicit correlations for turbulent flow friction factorBrkić, Dejan et al. | 2011
- 4060
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Comments on “Effect of uncertainties in best-estimate thermal hydraulic analysis on core damage frequency for PSA” Y.-J. Choa, T.-J. Kima, H.-G. Limb, G.-C. ParkaPourgol-Mohammad, Mohammad et al. | 2010
- iv
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Frontispiece| 2011
- v
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Contents| 2011