The pressure drop characteristics of humid air outside staggered tube bundles in the evaporative cooling process (English)
- New search for: Ma, Hongqiang
- New search for: Xie, Yue
- New search for: Liu, Yu
- New search for: Liu, Yemin
- New search for: Hou, Caiqin
- New search for: Luo, Xinmei
- New search for: Li, Qinghua
- New search for: Ma, Hongqiang
- New search for: Xie, Yue
- New search for: Liu, Yu
- New search for: Liu, Yemin
- New search for: Hou, Caiqin
- New search for: Luo, Xinmei
- New search for: Li, Qinghua
In:
Nuclear Engineering and Design
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395
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2022
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ISSN:
- Article (Journal) / Electronic Resource
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Title:The pressure drop characteristics of humid air outside staggered tube bundles in the evaporative cooling process
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Contributors:Ma, Hongqiang ( author ) / Xie, Yue ( author ) / Liu, Yu ( author ) / Liu, Yemin ( author ) / Hou, Caiqin ( author ) / Luo, Xinmei ( author ) / Li, Qinghua ( author )
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Published in:
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2022-06-12
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 395
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.
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Editorial Board| 2022
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Demonstration of a random sampling approach to uncertainty propagation for generic pebble-bed fluoride-salt-cooled high temperature reactor (gFHR)Walton, Noah A.W. / Crowder, Robert / Satvat, Nader / Brown, Nicholas R. / Sobes, Vladimir et al. | 2022
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Research on flow resistance characteristics of reactor coolant pump under large break LOCA at inletAn, Ce / Li, Huairui / Chen, Yiming / Zhu, Rongsheng / Fu, Qiang / Wang, Xiuli et al. | 2022
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Experimental and numerical study on the PHWR channel heat-up under an oxidizing environmentAjay, Ketan / Kumar, Ravi / Gupta, Akhilesh et al. | 2022
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Modeling of interfacial area for single deformed bubble based on VOF methodMei, Zhongkai / Cheng, Xu et al. | 2022
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Corrigendum to “Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: the Pacio-Chen-Todreas Detailed model (PCTD)” [Nucl. Eng. Des. 388 (2022) 111607]Pacio, J. / Chen, S.K. / Chen, Y.M. / Todreas, N.E. et al. | 2022
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Two-phase flow pressure drop modelling in horizontal pipes with different diametersFaraji, Foad / Santim, Christiano / Chong, Perk Lin / Hamad, Faik et al. | 2022
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New multi-fluid model of pool scrubbing in bubble rise regionKunšek, Matic / Cizelj, Leon / Kljenak, Ivo et al. | 2022
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The pressure drop characteristics of humid air outside staggered tube bundles in the evaporative cooling processMa, Hongqiang / Xie, Yue / Liu, Yu / Liu, Yemin / Hou, Caiqin / Luo, Xinmei / Li, Qinghua et al. | 2022
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A layered 2D computational framework: Theory and applications to nuclear fuel behaviorGamble, K.A. / Spencer, B.W. / Hales, J.D. / Knight, T.W. / Roberts, E. et al. | 2022
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Comparison and optimization of heat transfer models in reactor channel under the rolling conditionLi, Dong / Lin, Weicheng / Yan, Ting et al. | 2022
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Investigations on flow-regime characteristics during debris bed formation behavior in sodium-cooled fast reactor by releasing high-temperature particlesXu, Ruicong / Cheng, Songbai / Xu, Yihua / Tan, Yuecong / Zhang, Huaiqin et al. | 2022
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Out-of-sample validation of a general correlation for steam condensation in the presence of air over a vertical slender tube in turbulent free convectionDehbi, A. et al. | 2022
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The use of a novel gradient heat flux sensor for characterization of reflux condensationJanasz, Filip / Prasser, Horst-Michel / Suckow, Detlef / Mityakov, Andrey et al. | 2022
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Numerical modelling of the effect of appendages on turbulent mixing in connected nuclear fuel subchannelsBallyk, M. / Lightstone, M.F. / Tullis, S. et al. | 2022
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Validation of ASTEC2.1 using QUENCH-12 for VVER-ReactorsMercan, Ahmet Kağan / Sánchez-Espinoza, Victor Hugo / Gabrielli, Fabrizio et al. | 2022
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Thermal hydraulic analysis of the AFIP-7 irradiation test in the Advanced test Reactor – Model correlation and performance evaluationXing, Changhu / Jesse, Casey J. / Jones, Warren F. / Johnson, Maxine P. / Marie Phillips, Ann / Marshall, Theron D. et al. | 2022
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Demonstration of the model of physicochemical processes in heavy liquid metal cooled reactors in an example of the THEADES experiment simulationSergeenko, K. / Svirid, K. / Afremov, D. / Folomeev, V. et al. | 2022
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Evaluation of gas leaks from canisters by using a horizontal small-scale canister modelTakeda, Hirofumi / Shimizu, Kosuke et al. | 2022
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CFD analysis of water vapor condensation in large containments: Numerical model, verification and validationBieder, Ulrich / Herbette, Axelle et al. | 2022
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Neutronics design optimization of a small modular fast reactor based on response surface methodologyGao, Yucui / Cao, Liangzhi / Ye, Wenlian / Yan, Xuesong / Chen, Liangwen / Zhang, Yaling / Yang, Lei / Wang, Sheng et al. | 2022
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A simulation and machine learning informed diagnosis of the severe accidentsSong, JinHo / Ha, KwangSoon et al. | 2022
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Studies and cross-comparisons of severe accident prevention and mitigation capabilities of a SFR and a GFRBertrand, F. / Bachrata, A. / Seiler, N. / Droin, J.B. / Mouly, A. et al. | 2022
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Performance of different duct-nozzle arrangement on heat removal from a nuclear fuel storage vault under regular operating conditionsMishra, Vivek K. / Panda, Saroj K. / Sen, Biswanath / Maiya, M.P. / Rao, B.P.C. et al. | 2022
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The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundlesChen, Y.M. / Chen, S.K. / Hassan, Y. et al. | 2022
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Numerical simulation research on two-phase flow boiling heat transfer in helically coiled tubeWu, Jinxing / Li, Zhe / Li, Songge / Chen, Yabo / Liu, Shaolin / Xia, Chunjie / Chen, Yongdong et al. | 2022
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Recurrent neural network-based prediction of critical heat flux in rod bundles with non-uniform axial power shapeMarcinkiewicz, Krzysztof / Wieckhorst, Ole / Macián-Juan, Rafael / Rehm, Markus / Pohl, Peter et al. | 2022
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Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRsChen, Xingwei / Zou, Yang / Chen, Zehan / Dai, Ye et al. | 2022
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A surrogate machine learning model for advanced gas-cooled reactor graphite core safety analysisJones, H. Rhys / Mu, Tingting / Kudawoo, Dzifa / Brown, Gavin / Martinuzzi, Philippe / McLachlan, Neil et al. | 2022
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Experimental investigation of the pressure oscillations induced by subsonic steam jets under different vessel pressuresLiu, Xinxing / Yu, Mingrui / Li, Wei / Yu, Pei / Meng, Zhaoming / Sun, Zhongning / Zhang, Nan / Ding, Ming et al. | 2022
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Implementation of a comprehensive reduced order methodology for transient analysis of nuclear thermal propulsion enginesManickam, V. / Kotlyar, D. et al. | 2022
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Coupled simulations for prismatic gas-cooled reactorPodila, K. / Chen, Q. / Huang, X. / Li, C. / Rao, Y. / Waddington, G. / Jafri, T. et al. | 2022
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Artificial intelligence-driven thermal design for additively manufactured reactor coresPopov, Emilian / Archibald, Richard / Hiscox, Briana / Sobes, Vladimir et al. | 2022