14133 Design of Containment Filtered Venting System for Depressurization in Containment under Severe Accidents (Englisch)
- Neue Suche nach: Na, Y.S.
- Neue Suche nach: Ha, K.S.
- Neue Suche nach: Park, R.-J.
- Neue Suche nach: Park, J.-H.
- Neue Suche nach: Cho, S.-W.
- Neue Suche nach: American Nuclear Society
- Neue Suche nach: Na, Y.S.
- Neue Suche nach: Ha, K.S.
- Neue Suche nach: Park, R.-J.
- Neue Suche nach: Park, J.-H.
- Neue Suche nach: Cho, S.-W.
- Neue Suche nach: American Nuclear Society
In:
Advances in nuclear power plants
;
1068-1074
;
2014
-
ISBN:
- Aufsatz (Konferenz) / Print
-
Titel:14133 Design of Containment Filtered Venting System for Depressurization in Containment under Severe Accidents
-
Beteiligte:Na, Y.S. ( Autor:in ) / Ha, K.S. ( Autor:in ) / Park, R.-J. ( Autor:in ) / Park, J.-H. ( Autor:in ) / Cho, S.-W. ( Autor:in ) / American Nuclear Society
-
Kongress:International congress, Advances in nuclear power plants ; 2014 ; Charlotte, NC
-
Erschienen in:Advances in nuclear power plants ; 1068-1074INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS ; 2 ; 1068-1074
-
Verlag:
- Neue Suche nach: American Nuclear Society
-
Erscheinungsort:LaGrange Park, Illinois
-
Erscheinungsdatum:01.01.2014
-
Format / Umfang:7 pages
-
Anmerkungen:Includes bibliographical references and index; British Library not licensed to copy
-
ISBN:
-
Medientyp:Aufsatz (Konferenz)
-
Format:Print
-
Sprache:Englisch
-
Schlagwörter:
-
Datenquelle:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Inhaltsverzeichnis Konferenzband
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
- 801
-
14218 Simulation for New Builds. A Challenging but Essential Tool. Application to Atucha II NPPRey, P. / American Nuclear Society et al. | 2014
- 808
-
14243 Interactive Simulation and Visualization of Under-Sodium ViewingPark, Y.S. / Gima, Z.T. / Dworzanski, P. / Zhao, X. / Roberts, L. / Vilim, R.B. / American Nuclear Society et al. | 2014
- 815
-
14359 Flow Characteristics Analysis of Control Valve for Turbine SystemBhowmik, P.K. / Shamim, J.A. / Suh, K.Y. / American Nuclear Society et al. | 2014
- 822
-
14170 Improvements in the Testing of Instrumentation and Control SystemsFukumoto, A. / Hasegawa, T. / Odagawa, N. / Komine, K. / Takeda, T. / Porco, P.G. / Costantino, R.A. / American Nuclear Society et al. | 2014
- 829
-
14177 Traversing In-Core Probe (TIP) Replacement in BWR PlantMiyazaki, T. / Tarumi, T. / Yasuta, H. / Kelly, S.P. / American Nuclear Society et al. | 2014
- 834
-
14369 The Improvement and Validation of Setpoint Methodology for Diverse Protection SystemLee, C.J. / Park, M.S. / Lee, G.C. / Oh, Y.G. / Han, S. / Yun, J.H. / Baek, S.M. / Lee, S.J. / American Nuclear Society et al. | 2014
- 842
-
14373 Advancing On-Line Monitoring Capabilities for Sensor ValidationVilim, R.B. / Heifetz, A. / American Nuclear Society et al. | 2014
- 850
-
14008 Parameters Influencing the Hydrogen Concentration and Distribution in Cladding Tubes after LOCA: Results of Bundle-Scale Experiments and ModelingGrosse, M. / Stuckert, J. / Steinbrueck, M. / American Nuclear Society et al. | 2014
- 857
-
14018 Classification of Loss of Coolant Accident for Advanced Boiling Water ReactorLee, B.-H. / Chou, H.-P. / American Nuclear Society et al. | 2014
- 863
-
14021 Preliminary Evaluation of Re-Criticality Potential for ESFR Core and Conditions for Its EliminationPolidoro, F. / Flad, M. / Maschek, W. / American Nuclear Society et al. | 2014
- 872
-
14105 Particle Based Modeling of Fuel Plate Melting under Coolant Channel Flow BlockageNakamura, H. / American Nuclear Society et al. | 2014
- 880
-
14158 Verification of Core Exit Temperature for Adequate SAMG Entry Condition of OPR1000Seo, S. / Lee, S. / Kim, H.-Y. / Ha, K.S. / Jeun, G. / Kim, S.J. / American Nuclear Society et al. | 2014
- 889
-
14016 Simulation of Sodium Aerosol Behaviour with CONTAIN-LMR CodeGordeev, S. / Hering, W. / Schikorr, M. / Stieglitz, R. / American Nuclear Society et al. | 2014
- 895
-
14035 Simulation of PWR's Passive Containment Cooling with an Advanced Water Film ModelHuang, X. / Cheng, X. / American Nuclear Society et al. | 2014
- 905
-
14197 US-ABWR Design Capability During Extended Loss of AC Power EventsArai, K. / Thomas, S. / Mookhoek, B. / Powers, J. / Alford, W. / American Nuclear Society et al. | 2014
- 913
-
14265 A Probabilistic Safety Assessment of Ultimate Response Guidelines of Chinshan Nuclear Power PlantLai, H.-E. / Lee, M. / Chao, C.-C. / American Nuclear Society et al. | 2014
- 921
-
14113 Atmospheric Stability Classification of Dispersion Factor for Radiological Analysis at YONGGWANG Site in KOREALee, S.C. / Yoon, D.J. / Song, D.S. / American Nuclear Society et al. | 2014
- 930
-
14152 A Novel Guided Ultrasonic Wave Sensor for Quantitative Gas Accumulation Sensing in Nuclear Coolant PipesTian, Z. / Yu, L. / American Nuclear Society et al. | 2014
- 936
-
14202 Experimental Studies on the Revaporisation Behaviour and Aerosol Formation of Caesium under Severe Accident ConditionsKnebel, K. / Bottomley, P.D.W. / Rondinella, V.V. / Auvinen, A. / Jokiniemi, J. / American Nuclear Society et al. | 2014
- 943
-
14329 Sensitivity and Uncertainty Analysis for Predication of Particulate Debris Bed Self-Leveling in Prototypic SA ConditionsBasso, S. / Konovalenko, A. / Kudinov, P. / American Nuclear Society et al. | 2014
- 953
-
14330 Development of Scalable Empirical Closures for Self-Leveling of Particulate Debris BedBasso, S. / Konovalenko, A. / Kudinov, P. / American Nuclear Society et al. | 2014
- 960
-
14098 Application of RELAP/SCDAPSIM/MOD3.5 to a Representative BWR for Fukushima-Daichii-Like SBO TransientsAllison, C. / Hohorst, J. / Venturi, F. / Forgione, N. / Lopez, R. / American Nuclear Society et al. | 2014
- 970
-
14100 Development of Finite Element Models from Existing Lumped Mass Stick ModelsTorkian, B. / Chandran, P. / Ratnagaran, B.J. / Miller, R. / Lu, S. / American Nuclear Society et al. | 2014
- 978
-
14107 Tsunami PRA for Japan Sodium-Cooled Fast ReactorNishino, H. / Kurisaka, K. / Yamano, H. / Okano, Y. / Sakai, T. / American Nuclear Society et al. | 2014
- 988
-
14138 Research of Seawater Effects on Thermal-Hydraulic Behavior at Severe Accident-Research Plan and Thermal-Hydraulic Data in Annular TubeLiu, W. / Nagatake, T. / Jiao, L. / Takase, K. / Yoshida, H. / Nagase, F. / American Nuclear Society et al. | 2014
- 995
-
14194 Numerical Investigation of Fukushima Daiichi-2 SBO ScenarioChen, Y. / Ma, W. / Cui, L. / American Nuclear Society et al. | 2014
- 1004
-
14156 Remaining Issues in Pool Scrubbing: Major Drivers for Experimentation within the EU-PASSAM ProjectHerranz, L.E. / Tardaguila, R.D. / Torsten, B. / Lind, T. / Morandi, S. / American Nuclear Society et al. | 2014
- 1013
-
14209 MAAP Enhancements for Ascertaining and Analyzing Reactor Core Status in Fukushima-Daiichi NPPsKojima, Y. / Yanagisawa, H. / Shinji, N. / Horie, H. / Sakai, N. / Wachowiak, R. / Paik, C. / Plys, M. / American Nuclear Society et al. | 2014
- 1021
-
14376 Numerical Simulation of Dispersion and Deposition of Radionuclides over Ocean Sectors from Fukushima Dai-ichi Accidental ReleasesSrinivas, C.V. / Rakesh, P.T. / Prasad, K.B.R.R.H. / Venkatesan, R. / Ramakrishnan, B. / Venkatraman, B. / Murty, S.A.V.S. / American Nuclear Society et al. | 2014
- 1028
-
14388 Evaluation of ABWR for Safety Post-FukushimaPowers, J. / Arai, K. / Kuroda, M. / Thomas, S. / Mookhoek, B. / American Nuclear Society et al. | 2014
- 1036
-
14033 Robust and Resilent Severe Accident MitigationSong, J.H. / American Nuclear Society et al. | 2014
- 1047
-
14091 The Timing of Reactor Vessel Failure during the Severe Accident ProgressionVo, T.H. / Song, J.H. / Kim, T.W. / Kim, D.H. / American Nuclear Society et al. | 2014
- 1057
-
14108 Estimation Analysis of Pressure Loading in a Typical Chinese Pressurized Water Reactor Cavity During Ex-Vessel Steam ExplosionZhou, Y. / Lin, M. / Zhong, M. / American Nuclear Society et al. | 2014
- 1068
-
14133 Design of Containment Filtered Venting System for Depressurization in Containment under Severe AccidentsNa, Y.S. / Ha, K.S. / Park, R.-J. / Park, J.-H. / Cho, S.-W. / American Nuclear Society et al. | 2014
- 1075
-
14248 PLINIUS-2: A Versatile Platform for Severe Accident Mitigation Device and Simulation AssessmentsWillermoz, G. / Journeau, C. / Suteau, C. / Haquet, J.-F. / Piluso, P. / Buffe, L. / Pluyette, E. / Cassiaut-Louis, N. / Boyer, V. / Bottin, M. et al. | 2014
- 1082
-
14029 Development and Validation of a New Direct Containment Heating (DCH) Model for the Integral Code ASTECEckel, J. / Spengler, C. / American Nuclear Society et al. | 2014
- 1091
-
14078 Development of Calculation Method for Heat Flux from Molten Debris during In-Vessel RetentionAoki, K. / Sato, H. / Mizuguchi, K. / Okonogi, K. / Nishi, H. / American Nuclear Society et al. | 2014
- 1099
-
14080 Improvements of the Debris Spreading Model in SAMPSON Code and Evaluation for the Spreading on Primary Containment Vessel FloorHidaka, M. / Fujii, T. / Sakai, T. / Nakashima, K. / American Nuclear Society et al. | 2014
- 1107
-
14142 An Experimental Study on the Coolability of Stratified Debris BedsThakre, S. / Ma, W. / American Nuclear Society et al. | 2014
- 1113
-
14352 Benchmark of MCCI Model in MAAP5.02 against OECD CCI Experiment SeriesZhou, Q. / Paik, C.Y. / McMinn, P. / American Nuclear Society et al. | 2014
- 1123
-
14150 Results of the QUENCH-DEBRIS TestStuckert, J. / Grosse, M. / Onel, Y. / Rossger, C. / Steinbruck, M. / American Nuclear Society et al. | 2014
- 1129
-
14179 Evaluation Plan for Passive Debris Cooling System and Refractory LayerKurita, T. / Sasaki, I. / Sasaki, F. / Takahashi, Y. / Fujii, T. / Satou, Y. / American Nuclear Society et al. | 2014
- 1138
-
14286 Kaiga Atomic Power Station Containment Behaviors during Postulated Severe Accident along With SAGSharma, S.K. / Bhartia, D.K. / Mohan, N. / Malhotra, P.K. / American Nuclear Society et al. | 2014
- 1146
-
14366 Development of Surrogate Model for Prediction of Corium Debris AgglomerationKudinov, P. / Davydov, M. / American Nuclear Society et al. | 2014
- 1156
-
14052 On-the-Fly Sampling of Thermal Scattering S( alpha , beta ,T) Data for Monte Carlo CodesPavlou, A.T. / Wart, M. / Ji, W. / Trumbull, T.H. / American Nuclear Society et al. | 2014
- 1164
-
14096 Coupling of System Thermal-Hydraulics and Monte-Carlo Method for a Consistent Thermal-Hydraulics-Reactor Physics FeedbackWu, X. / Kozlowski, T. / American Nuclear Society et al. | 2014
- 1175
-
14126 Verification of Nuclear Calculation Methodology and Preliminary Uncertainty Qualification in a Sodium-Cooled Fast ReactorIkeda, K. / Homma, Y. / Moriwaki, H. / Ohki, S. / American Nuclear Society et al. | 2014
- 1184
-
14146 Modeling of Reactivity Effects and Non-Uniform Axial Expansion of SFR Core on Basis of Neutronics Model with Constant Calculation MeshPonomarev, A. / Sanchez, V. / American Nuclear Society et al. | 2014
- 1191
-
14223 TRIPOLI-4 Simulation of Core Physics Parameters for Two 3600 MWt Sodium-Cooled Fast ReactorsLee, Y.-K. / Brun, E. / Alexandre, X. / American Nuclear Society et al. | 2014
- 1200
-
14025 Generation and Application of Interface Discontinuity Factors in the Reactor Simulator DYN3DDaeubler, M. / Jimenez, J. / Sanchez, V. / American Nuclear Society et al. | 2014
- 1210
-
14055 Latest Development of Core Simulator in COSINE Code PackageChen, Y. / Hu, X. / Wang, S. / Quan, G. / Wang, C. / Liu, Z. / Yu, H. / American Nuclear Society et al. | 2014
- 1216
-
14186 Improvement and Assessment of Stiffness Confinement Method with Pseudo AbsorptionPark, B.W. / Joo, H.G. / American Nuclear Society et al. | 2014
- 1225
-
14188 Control Rod Decusping Treatment based on Local 3-D CMFD Calculation for Direct Whole Core Transport SolversJung, Y.S. / Ban, Y.S. / Joo, H.G. / American Nuclear Society et al. | 2014
- 1232
-
14288 Sensitivity and Uncertainty Analysis of UO2 and MOX Fueled PWR Cells by Taking Account of Resonance Self-Shielding EffectTakeda, T. / Foad, B. / American Nuclear Society et al. | 2014
- 1238
-
14344 Fuel Performance Assessment when Modeling Gamma-Ray Heating During Steady-State and Transient ScenariosPorter, I.E. / Knight, T.W. / American Nuclear Society et al. | 2014
- 1245
-
14124 Analysis of the Behavior of BWR Core and Fuel with SiC Cladding and Channel BoxKitano, K. / Ban, Y. / Sakurai, S. / Inoue, F. / Uchihashi, M. / Ukai, M. / American Nuclear Society et al. | 2014
- 1254
-
14137 Study on Intra-Fuel Assembly Reshuffling Options in PWR In-Core Fuel ManagementDaing, A.T. / Kim, M.H. / American Nuclear Society et al. | 2014
- 1263
-
14145 Increasing the Fuel Utilization in Gen-II BWR with Reduced-Moderation Square Lattice Fuel AssembliesSchlenker, M.T. / Sanchez-Espinoza, V.H. / American Nuclear Society et al. | 2014
- 1272
-
14232 SLIMM - Neutronics Analysis and Lifetime EstimatesEl-Genk, M.S. / Palomino, L.M. / American Nuclear Society et al. | 2014
- 1281
-
14255 Comparison of the Reactivity Evolutions of Heterogeneous and Classical ASTRID Cores during Severe AccidentsPrulhiere, G. / Bertrand, F. / Maliverney, B. / American Nuclear Society et al. | 2014
- 1291
-
14308 Non-Invasive Imaging of a Reactor Using Cosmic-ray MuonsKume, N. / Miyadera, H. / Ban, Y. / Karino, Y. / Nakayama, K. / Sano, Y. / Sugita, T. / Yoshioka, K. / Morris, C.L. / Bacon, J.D. et al. | 2014
- 1297
-
14238 Interaction Experiments of Molten Corium with Structures in a Severe AccidentAn, S.M. / Ha, K.S. / Hong, S.H. / Kim, H.Y. / Cha, Y. / American Nuclear Society et al. | 2014
- 1302
-
14239 Coolability of an Ex-vessel Core Catcher Induced by Natural Circulation FlowHa, K.S. / Rhee, B.W. / Park, R.J. / American Nuclear Society et al. | 2014
- 1308
-
14314 An Evaluation of the Scaling Analysis Model of the EU-APR1400 Core Catcher Cooling System Test Facility Based on Test ResultsRhee, B.W. / Ha, K.S. / Park, R.J. / Song, J.H. / American Nuclear Society et al. | 2014
- 1314
-
14322 OECD/NEA HYMERES Project: For the Analysis and Mitigation of a Severe Accident Leading to Hydrogen Release into a Nuclear Plant ContainmentPaladino, D. / Mignot, G. / Kapulla, R. / Paranjape, S. / Andreani, M. / Studer, E. / Brinster, J. / Dabbene, F. / American Nuclear Society et al. | 2014
- 1323
-
14032 A Coupled RELAP5-3D/STAR-CCM+ Simulation for the Calculation of Friction Factor in PipesPalazzi, A. / Bluck, M.J. / Lo, S. / American Nuclear Society et al. | 2014
- 1330
-
14046 Numerical Simulation of Flow with Volume Condensation in Presence of Non-Condensable Gases within a PWR ContainmentZhang, J. / Laurien, E. / American Nuclear Society et al. | 2014
- 1341
-
14051 CFD Analysis on the Natural Circulation Cooling of a Spent Fuel PoolKelm, S. / Jahn, W. / Allelein, H.-J. / American Nuclear Society et al. | 2014
- 1350
-
14168 CFD Simulations of Thermal Stratification in a Large EnclosureCarasik, L.B. / Ruggles, A.E. / Walker, S.A. / American Nuclear Society et al. | 2014
- 1360
-
14191 A Study on Thermal Mixing Behavior in IRWST Using Three-Dimensional CFD AnalysisHa, J.H. / Lee, D.Y. / Hong, S.J. / Jeong, J.S. / Park, M.H. / Moon, Y.T. / American Nuclear Society et al. | 2014
- 1371
-
14326 CFD Simulations of Temperature Distribution in the Cavity Pool of an Ex-Vessel Cooling SystemDave, A. / Cramer, K. / Petrov, V. / Manera, A. / American Nuclear Society et al. | 2014
- 1378
-
14356 CFD Simulations of the Effects of Thermal Stratification on the Start of Natural Circulation during SFR TransientsMunkhzul, E. / Thomas, J. / American Nuclear Society et al. | 2014
- 1385
-
14401 Analysis of Thermalhydraulic Characteristics of AP1000 Passive Residual Heat Removal Heat ExchangerXie, X. / Tian, W. / Yu, P. / Nie, C. / Zhan, L. / Li, P. / American Nuclear Society et al. | 2014
- 1393
-
14023 A GEN-II Subcooled Boiling Model for CASL VERA Multiphase SimulationsGilman, L. / Baglietto, E. / American Nuclear Society et al. | 2014
- 1403
-
14081 The Hydrodynamics of Two-Phase Flow in a Tube Bundle and a Bare ChannelBetschart, T. / Suckow, D. / Brankov, V. / Prasser, H.-M. / American Nuclear Society et al. | 2014
- 1412
-
14087 Three-Dimensional Simulation of Natural Circulation in a Passive Condensate Cooling Tank of a Passive Feedwater Auxiliary System using the CUPID CodeLee, S.-J. / Cho, H.-K. / Park, I.K. / Yoon, H.-Y. / American Nuclear Society et al. | 2014
- 1418
-
14159 LES VOF Simulations of Annular Flow in a Double Subchannel with Swirl Type SpacerSaxena, A. / Prasser, H.-M. / American Nuclear Society et al. | 2014
- 1426
-
14295 Multiphase and Turbulence Models' Sensitivity Study in Pressurized Thermal Shock Simulations of the TOPFLOW ExperimentDeshpande, S.S. / Niceno, B. / Mutz, A. / Klugel, J. / American Nuclear Society et al. | 2014
- 1436
-
14089 Study of Strongly Heated Upward Turbulent Gas FlowNietiadi, Y.S. / Lee, J.I. / Addad, Y. / American Nuclear Society et al. | 2014
- 1445
-
14090 Identification of Asymmetry Reactor Flow Characteristics for a Single Pump Failure Condition with 1/5 Scale linearly Reduced Facilities Referring to APR+Euh, D.J. / Kim, K.H. / Kwon, T.S. / Chu, I.C. / Choi, H.S. / Lee, S.T. / American Nuclear Society et al. | 2014
- 1452
-
14161 Experimental Investigation on Hydrodynamic Phenomena Associated with Postulated Vapor Explosion Scenarios in the Phenix ReactorSemeraro, E. / Bucci, M. / Cariteau, B. / Magnaud, J.-P. / Monavon, A. / American Nuclear Society et al. | 2014
- 1460
-
14203 Development of a Prototypical Condensation Model for the Nearly Horizontal Heat Exchanger Tube of the APR+ PAFS (Passive Auxiliary Feed-water System)Ahn, T.-h. / Yun, B.-J. / Jeong, J.-J. / Kang, K.-h. / Park, Y.-s. / Cheon, J. / American Nuclear Society et al. | 2014
- 1468
-
14235 LOFT L9-3 Experiment Simulation Using the SPACE CodeYang, C.-K. / Kim, Y.-H. / Ha, S.-J. / American Nuclear Society et al. | 2014
- 1475
-
14043 Experiment Study on Flow Characteristics of Free Falling Wafer Film on Steel PlateHu, P. / Huang, X. / Bao, K. / Zhu, G. / American Nuclear Society et al. | 2014
- 1480
-
14229 Measurement of the Minimum Film Boiling Temperature for Low Pressure and Low-Flow Rate Flow BoilingKim, B.J. / Park, J.S. / Park, J.K. / Moon, S.K. / Kim, K.D. / Kim, H.D. / Heo, J.S. / American Nuclear Society et al. | 2014
- 1486
-
14257 Advanced Calibration and Validation of a Mechanistic Model of Subcooled Boiling Two-Phase FlowBui, A. / Williams, B. / Dinh, N. / American Nuclear Society et al. | 2014
- 1494
-
14395 Off-normal Characteristic Two-Phase Flow Behavior in the Water-Cooled MHTGR-RCCS with Decay Heat VariationOmotowa, O. / Lisowski, D. / Anderson, M. / Tokuhiro, A. / Corradini, M. / American Nuclear Society et al. | 2014
- 1502
-
14149 Numerical Study of Three-Dimensional Steam-Water Flows in Circulation Loops of VVER-Type Reactors with Best Estimate Thermal Hydraulic Code BAGIRAKroshilin, V.E. / Kroshilin, A.E. / Pryakhin, V.N. / Smirnov, A.V. / American Nuclear Society et al. | 2014
- 1513
-
14227 Implementation and Validation of COBRA-TF Subcooled/Nucleate Boiling ModelsCao, L. / Sung, Y. / Kucukboyaci, V. / American Nuclear Society et al. | 2014
- 1518
-
14334 On Post-Dryout Heat Transfer in Channels with Flow ObstaclesAnglart, H. / Anghel, I.G. / American Nuclear Society et al. | 2014
- 1524
-
14351 Assessment of Subchannel Code ASSERT-PV for Prediction of Post-Dryout Heat Transfer in CANDU BundlesCheng, Z. / Rao, Y.F. / Waddington, G.M. / American Nuclear Society et al. | 2014
- 1532
-
14354 Assessment of Subchannel Code ASSERT-PV for Prediction of Critical Heat Flux in CANDU BundlesRao, Y.F. / Cheng, Z. / Waddington, G.M. / American Nuclear Society et al. | 2014
- 1540
-
14157 Two-loop PWR RELAP5 to TRACE Model Conversion and Three Dimensional Vessel Model Development for Coolant Mixing AnalysisBerar, O.-A. / Prosek, A. / Leskovar, M. / Mavko, B. / American Nuclear Society et al. | 2014
- 1547
-
14347 Development of Sub-Channel Spacer Model and Evaluation of Existing Spacer Models in Single and Two Phase FlowAydogan, F. / Cannon, J. / American Nuclear Society et al. | 2014
- 1558
-
14357 Prediction of Subchannel Mixing Downstream of Spacer GridsKaroutas, Z.E. / Yan, J. / Joffre, P.F. / Yuan, P. / American Nuclear Society et al. | 2014
- 1565
-
14363 TRACG Analysis of the OECD/NEA Oskarshamn-2 BWR Stability Benchmark Based on February 25, 1999 Feedwater Transient EventCowen, H.M. / Pfeffer, S.L. / Vedovi, J. / Ibarra, L. / Vreeland, D.G. / Miranda, D.C. / American Nuclear Society et al. | 2014
- 1574
-
14027 Unsteady Bulk Boiling in a Tall and Slender Water PoolLaurien, E. / Kutnjak, J. / American Nuclear Society et al. | 2014
- 1586
-
14103 Development of Accurate and Stable Two-Phase Two-Fluid Model SolverSaleem, R.A.A. / Kozlowski, T. / American Nuclear Society et al. | 2014
- 1595
-
14115 Numerical Analysis of Molten Droplet Pre-Conditioning under High Pressure PulseZhong, M. / Lin, M. / Xiong, J. / Yang, Y. / American Nuclear Society et al. | 2014