会议专题

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

总文献量: 243篇会议类型: 国际会议会议地点: 上海主办单位: 中国核学会会议日期: 2010-10-10

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Potential Improvements of Supercritical CO2 Brayton Cycle by Mixing Other Gases with CO2

Woo Seok Jeong Jong Hyuk Lee Jeong Ik Lee Yong Hoon Jeong Hee Cheon NO Ji Hwan Kim

Assessment of the Wall Condensation Heat Transfer Models for the SPACE Code

Hyun-Sik Park Jung-Woo Kim Ki-Yong Choi Sang-Ki Moon Kyung-Doo Kim

Study of VVER Steam Generator Operation in Condensation Mode with Non-condensable Gases Effect in Case of Twenty-four-hour Accident Process

A.V. Morozov O.V. Remizov A.A. Tsyganok D.S. Kalyakin

Effect of Pressure Tube Radial Creep on Thermal Hydraulic Performance of Pressure Tube Type Nuclear Reactors

Arnab Dasgupta D.K. Chandraker P.K. Vijayan

Computational Validation of the EPRTM Combustible Gas Control System

Harald Dimmelmeier Jürgen Eyink Mohammad-Ali Movahed

Uncertainty and Sensitivity Analysis for the High Performance Light Water Reactor with TRACE and SUSA

Wadim Jaeger Victor Hugo Sánchez Espinoza Lanfranco Monti Antonio Hurtado

The Experimental Study of The Single Molten Metal Droplet Breakup in Coolant

Tianshu Li Yanhua Yang Lihong Xu

On the Applicability of a One-Dimensional Two-Fluid Flow Model to Simulation of Flows and Heat Transfer at Near- and Supercritical Pressures

Joona Kurki Markku H(a）nninen

Heat transfer characteristics of one side heated vertical rectangular channel

Tetsuaki Takeda Akira Honma Yuta Sugai Koji Toriyama

Sensitivity Analysis of CFD Two-Phase Flow in a BWR Fuel Bundle

M. Jaromin T. Kozlowski H. Anglart

Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (5) Development of Technical Basis for the Protected Loss of Heat Sink

Yoshiharu Tobita Hidemasa Yamano

MSIV COMPARTMENT PRESSURE RESPONSE TO MSLB WITH TMD CODE

ZHANG Guosheng

An Evaluation of RCS Depressurization before Reactor Vessel Failure by using SCDAP/RELAP5

Rae-Joon Park Kyung-Ho Kang Seong-Wan Hong

Research on velocity distributions in a steam-driven turbulent jet in a subcooled water

Xinzhuang WU Junjie YAN Wenjun LI Dongdong PAN Guangyao LIU

Validation of the MCCI-Code MEDICIS against the Experiment COMET-L2

Gert Sdouz Hans Alsmeyer

Analysis of Nuclear Seawater Desalination Reactor Passive Safety System Facility Emergency Residual Heat Removal Test

Xu Shijie Liu Xun Nie Changhua Zhuo Wenbin Zheng Hua

Study of the CPR1000 Containment Over-pressure Fragility Curve and improvement of Containment Filtration and Exhaust System

Jiming LIN Peng CHEN Shishun ZHANG

Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (1) Overview of Evaluation Technology Development

Ryodai Nakai Tohru Suzuki Kenji Kamiyama Hiroshi Seino Kazuya Koyama Koji Morita

Study on the Resistance Characteristics of Two-Phase Flow through Non-Heat-Generating Porous Media

Zhang Zhen Yan Xiao Xiao Ze-jun Liu Xiang-feng

Assessment of the Wall and Interphase Friction Modules in SPACE Code

B. J. Kim M. K. Hwang K. D. Kim S. W. Lee