Is Reactor Multiphase Thermal-Hydraulics a Mature Field of Engineering Science? (English)
- New search for: Podowski, Michael
- New search for: Podowski, Michael
In:
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 14 of 14
; 8142-
;
2018
- Conference paper / Print
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Title:Is Reactor Multiphase Thermal-Hydraulics a Mature Field of Engineering Science?
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Contributors:Podowski, Michael ( author )
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Conference:NURETH ; 17. ; 2017 ; Xi'an
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Published in:
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Publisher:
- New search for: Curran Associates, Inc.
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Place of publication:Red Hook, NY
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Publication date:2018
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Source:
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.
- 7811
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High Resolution Velocity Field Measurements of Turbulent Round Free Jets in Uniform EnvironmentsQin, Sunming / Krohn, Benedikt / Downing, John / Petrov, Victor / Manera, Annalisa et al. | 2018
- 7825
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Interaction of Parallel Rectangular Jets in the Recs Separate-Effects Test FacilityNunez, Daniel / Krohn, Benedikt / Petrov, Victor / Manera, Annalisa et al. | 2018
- 7837
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Nuclear Reactor Modeling and Simulation Tookit(NUREMOST)Batra, Chirayu / Kriventsev, Viadimir / Jevremovic, Tatjana / Monti, Stefano et al. | 2018
- 7847
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Verification of The Erosion Phenomena of Helium StratificationKang, Gilbeom / Hong, Tae-Hyub et al. | 2018
- 7859
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Comparison of Modified ART MOD 2 Code with Phébus FPT-3 Experiment: Evaluation of Volatile Aerosol Behaviors in Containment VesselVechgama, Wasin / Silva, Kampanart et al. | 2018
- 7869
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Towards the Direct Numerical Simulation of a Single Phase Pressurized Thermal ShockShams, Afaque / Komen, E. M. J. et al. | 2018
- 7883
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Modeling of Buoyancy-Driven Flow Mixing Experiments in Rocom Test Facility Using 3D Capabilities of CATHARE CodeLutsanych, Sergii / D'Auria, Francesco et al. | 2018
- 7897
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Assessment of COBRA-IE Code Capabilities in Modeling Fluid Mixing and Multidimensional Flow using Data from the International Standard Problem 43(ISP-43)Gosdin, Christopher A. / Frepoli, Cesare / Aumiller, David L. / Buschman, Francis X. et al. | 2018
- 7912
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A Comparative Study of Boron Transport in Thermal-Hydraulic Codes TRACE Vs TRAC-BF1 and RELAPOlmo-Juan, Nicolás / Barrachina, Teresa / Miro, Rafael / Pereira, Claubia / Verdi, Gumersindo J. / Querol, A. et al. | 2018
- 7925
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Benchmark of CFD Methodology for Boron Dilution Simulation based on ROCOM ExperimentHan, Xu / Xiong, Jinbiao / Cheng, Xu et al. | 2018
- 7936
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Strainer Blockage Evaluation and Improvement in Maanshan Nuclear Power Plant for Resolving GSI-191 IssueLin, Yon-Pon / Hu, Hsiang-Cheng / Kuo, Mu-Chin et al. | 2018
- 7950
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Analysis of the Reactor Coolant System Depressurization After Severe AccidentsJiang, Pingting et al. | 2018
- 7957
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The Prediction and Diagnosis for CPR1000 Accidents Based on ANNSLi, Shi-Xian / Liu, Jing-Quan / Shen, Yong-Gang et al. | 2018
- 7970
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Analysis of the DVI Line Break Accident of the Westinghouse SMR with SPECTRA, MELCOR and RELAP System CodesStempniewicz, M. M. / Alcaro, F. / Geus, P. A. Breijder. E. A. R. de / Smith, M. C. / Kucukbovaci, V. N. et al. | 2018
- 7984
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Recent Progress in Mechanistic Understanding of Nucleate Boiling PhenomenaSong, Chul-Hwa / Chu, In-Cheol / Hoang, Nhan Hien et al. | 2018
- 8004
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Rod Bundie Heat Transfer Thermal-hvdraulics ProgramBajorek, Stephen M. et al. | 2018
- 8037
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CFD Modelling of Annular Two-Phase Flow and Heat TransferAnglart, Henryk et al. | 2018
- 8063
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Experimental Needs for Computational Fluid Dynamics Validation for Nuclear ApplicationsHassan, Yassin A et al. | 2018
- 8064
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The Remaining and Future Challenges for Nuclear Thermal HydraulicsSehgal, Bal Raj et al. | 2018
- 8066
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Liquid Film Measurements Using Electrical Sensors, Infrared Attenuation and Tomography with Neutrons and X- raysPrasser, Horst-Michael et al. | 2018
- 8095
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Observation-based CHF Model Development: Dry Spot - Dry Patch Models seenNo, Hee Cheon / Ha, Sang-Jun / Chu, In-Cheol / Choi, Jin Young et al. | 2018
- 8106
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Visualization of Eutectic Phenomena During Severe AccidentOkamoto, Koji / Ueda, Shota et al. | 2018
- 8112
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Assembling the Second Generation Multiphase-CFD Closures, One Bubble at a TimeBaglietto, Emilio et al. | 2018
- 8138
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Perspectives on the Future of Nuclear Power In the United StatesKelly, John et al. | 2018
- 8142
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Is Reactor Multiphase Thermal-Hydraulics a Mature Field of Engineering Science?Podowski, Michael et al. | 2018
- 8161
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Numerical Simulation of Complete Pool Boiling Curves: From Nucleation to Critical Heat Flux Through Transition Boiling to Film BoilingCheng, Ping et al. | 2018
- 8171
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CFD Analysis of Wave influence on Falling Film CondensationWang, Xianmao / Chang, Huajian et al. | 2018
- 8172
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Description of the New RELAP/SCDAPSIM/MOD3.4 Capabilities for the Simulation of Severe Accident Scenarios with Best Estimate Codes in Full Scope and Simulator EnvironmentsMartinez-Quiroga, V. / Fu, Z. / Tan, Chao / Chen, Yunlong / Allison, C. M. / Hohorst, J. K. et al. | 2018
- 8173
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VOF Simulation on Single Bubble Rising in a Linear Shear Flow with Adaptive Mesh AlgorithmLee, W. R. / Lee, J. Y. et al. | 2018
- 8174
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Alisa Project: Access to Large Infrastructures for Severe Accidents in Europe and in ChinaMiassoedov, A. / Gaus-Liu, X. / Journeau, C. / Liao, Y. et al. | 2018
- 8175
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An Experimental Study on Measuring Volumetric Void Fraction Using Impedance Meter in 3x3 Rod Bundle Consisting of Metal FilterLee, Jong Wook / Kim, Han Sol / Lee, Jae Young / Euh, Dong Jin / Kim, Jong Rok et al. | 2018
- 8176
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Experimental Investigation of a Power Transient Influence on the Hot Water Layer in a Scaled Model of the Multipurpose Brazilian ReactorTomaz, Gabriel C. Q. / Matozinhos, Camila F. / Salomao, Eduardo A. / Santos, Andre A. C. Dos / Veloso, Maria A. F et al. | 2018
- 8177
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A Multi-physics Modelling Approach for the Evaluation of the Gas Bubbling System in the Molten Salt Fast ReactorCervi, Eric / Lorenzi, Stefano / Cammi, Antonio / Luzzi, Lelio et al. | 2018
- 8178
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Systematic Process to Determine DNBR Limit of CHF Correlation with Repetitive Cross-validation TechniqueKim, Byeungseok / Park, Shane / Kim, Kanghoon / Lim, Jongseon / Nahm, Keeyil et al. | 2018
- 8179
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Acceptance Criterion for Repeated Critical Heat Flux DataKim, KangHoon / Lim, JongSeon / Nahm, KeeYil / Clement, Philippe / Cubizolles, Geraud et al. | 2018
- 8180
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Application of DTS Analysis Method for HPR1000Zhang, Yubin / Li, Qiang / Wang, Xiong / Wang, Ting et al. | 2018
- 8181
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Simulation of Jet Flow Obstruction Interaction of Stratification Erosion in ContainmentZhang, Rong-jin / Li, Xiang / Fu, Xiao-Liang / Yang, Yan-hua et al. | 2018
- 8182
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A New Approach to the Numerical Simulation of Mixed Convection Heat Transfer in Supereritical FluidsBae, Y. Y. / Kim, E. S. / Kim, M. H. et al. | 2018
- 8183
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Simulation of Steam Generator Tube Rupture Accident in a VVER-1000 Nuclear Power PlantShome, D. / Sarkar, M. A. R. et al. | 2018
- 8184
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In-Vessel Melt Retention with External Cooling for VVER-1000Sholudko, A. / Balashevskyi, O. et al. | 2018
- 8185
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Observation of Water-vapor Two-phase Flow in Porous Media by CFD for the Design of a Printed Circuit Steam Generator (PCSG).......................Chen, L. S. / Lee, J. Y. et al. | 2018
- 8186
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Development of Severe Accident Process Simulation and Emergency Decision Support System for AP1000 Nuclear Power PlantJiang, Gang / Chen, Gang / Yan, Dagiang / Chen, Yixue / Yang, Yanhua et al. | 2018
- 8187
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A Numerical Study of Supercritical Carbon Dioxide Critical Flow| 2018
- 8188
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Inverse Uncertainty Quantification of Physical Model Parameters in Trace Using FEBA ExperimentHu, Guojun / Kozlowski, Tomasz et al. | 2018
- 8189
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Extension, Verification and Validation of the Molten Salt Contact with Non-Condensable Gas Problem on RELAP/SCDAPSIM/MOD4.0 CodeJiang, Shuying / Fu, Zheng / Allison, C. M. M. / Cheng, Maosong / Hohorst, J. K. et al. | 2018
- 8190
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Sub-compartments Overheat Risk Evaluation Without Cooling SystemZhou, Xiao / Wang, Jun / Dong, Jianhua et al. | 2018
- 8197
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Force Balance Analysis for Lift-off of Vapor Bubble Sliding on a Heated Horizontal Tube SurfaceKim, Yu-Na / Kim, Jae Soon / Park, Goon-Cherl / Cho, Hyoung Kyu et al. | 2018
- 8211
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Experimental Study ou HX Tube Rupture Accident for China Lead alloy-Cooled ReactorSa, Rongyuan / Zhou, Danna / Jiang, Hualei / Huang, Qunying et al. | 2018
- 8212
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CFD Analysis of the Natural Circulation Capability of KYLIN-II Liquid Lead Bismuth LoopChen, Liuli / Jiang, Zhizhong / Wu, Qingsheng et al. | 2018
- 8213
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Thermal-hydraulic Behavior of Wire-spaced Fuel Assembly Cooled with HLMZhou, Tao / Lyu, Kefeng / Jin, Ming / Liu, Shuyong / Bai, Yunging et al. | 2018
- 8214
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Conceptual Design of Condenser Using PCM As PCCS for Light Water ReactorsJung, H. Y. / Ko, A. R. / Lee, J. I. / Yoon, H. J. et al. | 2018
- 8221
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Comparison of Melcor and Corquench Modellings for Melt Coolability in Calandria Vault of PHWRYu, Seon Oh / Lee, Kyu Byung / Kim, Sung Jung et al. | 2018
- 8230
-
Study on Surface Effect on High Subcooled CHFLiu, Xirui / Yang, Bao-Wen et al. | 2018
- 8241
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MARS-LMR Node Sensitivity Analysis of Heat Exchangers in STELLA-2 FacilityLee, Jewhan / Kim, Hyungmo / Lee, Yong-Bum / Eoh, Jaehyuk / Jeong, Ji-Young et al. | 2018
- 8254
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Study on the Lateral Velocity and Vortex in Spacer GridHan, Bin / Yang, Bao-Wen / Wei, Cen / Zha, Yudong et al. | 2018
- 8262
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Comparison of the Effects of Different Types of Welding NuggetsYang, Bao-Wen / Wei, Cen / Han, Bin / Zha, Yudong et al. | 2018
- 8273
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Rod-to-wall Gap Calculation Through CFD ModelingLyu, Hongmei / Yang, Bao-Wen / Han, Bin et al. | 2018
- 8287
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The Influence of Mixing Vane Shapes on Flow Field in Rod BundlesMao, Hu / Yang, Bao-Wen / Lyu, Hongmei / Wei, Cen et al. | 2018
- 8296
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The Influence of Guide Tube Diameters ou Flow Field in Rod BundlesMao, Hu / Yang, Bao-Wen / Liu, Xirui et al. | 2018
- 8307
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The Influence of Non-uniform Heating on Two-phase Flow Instability in Open ChannelWang, Sipeng / Yang, Bao-Wen / Mao, Hu et al. | 2018
- 8319
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Thermodynamic Performance of Brayton Cycle Energy Conversion System of SpacecraftFeng, Z.-Y. / Li, H.-C. Zhang. X.-Q. / Cheng, X.-W. / Zhao, G.-B. et al. | 2018
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An Experimental Study on Measuring Volumetric Void Fraction Using Impedance Meter in 3x3 Rod Bundle Consisting of Metal Filterconsisting of Metal FilterLee, Jong Wook / Kim, Han Sol / Lee, Jae Young / Euh, Dong Jin / Kim, Jong Rok et al. | 2018
- 8343
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Direct Temperature Measurement Method of Nuclaer Reactor Graphite CoreRen, Cheng / Feng, Xiaojuan / Zhang, Jintao / Yang, Xingtuan et al. | 2018
- 8348
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Heat Loss Simulations in Large Scale Rod Bundle TestsLiu, Aiguo / Yang, Bao-Wen / Zha, Yudong et al. | 2018
- 8362
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Void Fraction Distribution and Code-to-code Comparison of Subcooled Boiling in a 5x5 Rod BundleHan, Bin / Yang, Bao-Wen / Wei, Cen / Zha, Yudong et al. | 2018
- 8363
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Experimental Study on Turbulent Enhanced Heat Transfer of Molten Satl in Transversally Grooved TubeChen, Y. S. / Zhu, H. H. / Tian, J. / Fu, Y. / Tang, Z. F. / Wang, N. X. et al. | 2018
- 8375
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Experimental Study of CLOF Test by SMART-ITL with PRHRSYang, Jin-Hwa / Bae, Hwang / Ryu, Sung-Uk / Jeon, Byong Guk / Yi, Sung-Jae / Park, Hyun-Sik et al. | 2018
- 8385
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Corium-Sodium Interaction: The Development of the Scone SoftwareZabiego, Magali / Fochesato, Christophe et al. | 2018
- 8399
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Analysis of an Electromagnetic Pump for Sodium Thermohydraulic Test in the Prototype Gen-IV Sodium Cooled Fast ReactorKim, Hee Reyoung / Kwak, Jaesik et al. | 2018
-
The Development of CAPs and Buildup of National CapabilityZheng, Mingguang et al. | 2018
-
Application of VOSET for Simulations of Boiling Heat TransferTao, Wenquan et al. | 2018
-
Progress in the Research and Development on Nuclear Reactor Thermal-Hydraulics and ChallengesHuang, Yanping et al. | 2018
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Homogeneous Nucleation Model for Rod Bundle CHFYang, Bao-wen et al. | 2018
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Benchmarking of COSINE codeYang, Yanhua et al. | 2018