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Development of Modeling Capabilities for the Analysis of Supercritical Water-Cooled Reactor Thermal-Hydraulics and Dynamics

机译：超临界水冷堆热工水力学与动力学分析建模能力的开发

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Podowski, Dr. Michael Z.;
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年度 2009
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1. Development of Three-Dimensional Thermal-Hydraulic Analysis Code for Supercritical Water-Cooled Reactor [J] . Takeharu Misawa, Hiroyuki Yoshida, Hidesada Tamai, Transactions of the American nuclear society . 2007,第Nov期

机译：超临界水冷堆三维热工水力分析程序的开发
2. Development of thermal-hydraulic analysis methodology for multiple modules of water-cooled breeder blanket in fusion DEMO reactor [J] . Kim Geon-Woo, Lee Jeong-Hun, Cho Hyoung-Kyu, Fusion Engineering and Design . 2016,第Feba期

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3. Development of a thermal-hydraulic analysis code for the Pebble Bed Water-cooled Reactor [J] . Xiaoyu Cai, Suizheng Qiu, Wenxi Tian, Nuclear Engineering and Design . 2011,第12期

机译：卵石床水冷堆热工水力分析代码的开发
4. THERMAL-HYDRAULIC ANALYSIS OF HEAT TRANSFER IN SUBCHANNELS OF THE EUROPEAN HIGH PERFORMANCE SUPERCRITICAL WATER-COOLED REACTOR FOR DIFFERENT CFD TURBULENCE MODELS [C] . Landy Y. Castro, Leorlen Y. Rojas, Abel Gamez, International Nuclear Atlantic Conference . 2018

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5. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications. [D] . Mokry, Sarah. 2009

机译：超临界水冷反应堆应用中超临界水传热相关性的发展。
6. The implementation of SOMO (SOlution MOdeller) in the UltraScan analytical ultracentrifugation data analysis suite: enhanced capabilities allow the reliable hydrodynamic modeling of virtually any kind of biomacromolecule [O] . Emre Brookes, Borries Demeler, Camillo Rosano, -1

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7. Development of Mechanistic Modeling Capabilities for Local Neutronically-Coupled Flow-Induced Instabilities in Advanced Water-Cooled Reactors [O] . Podowski, Michael 2009

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Development of Modeling Capabilities for the Analysis of Supercritical Water-Cooled Reactor Thermal-Hydraulics and Dynamics

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