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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Severe Accident Management and Research at CGNPC

Min Xiao Shishun Zhang Jiliang Sun Jiming Lin

New ideas for analyzing transient heat transfer characteristics of pulse reactor

Jinfeng PENG Fuyu ZHAO

One equation subgrid model for liquid metal forced convection

Ivan Oti?

EPZDose, An Evaluation Code for Radioactive Materials Dispersion And Dose Consequences in Nuclear Emergency Situations

Yi-Hsiang Cheng Wei-Cheng Wang Chia-Ying Chang Shao-Shuan Chen Chunkuan Shih

Natural Circulation Patterns in the VHTR Air-Ingress Accident and Related Issues

Chang H. Oh Eung S. Kim Hyung S. Kang

Analytical model for CHF in narrow gaps concerning surface orientation effects

Y. P. Zhang W. X. Tian S. Z. Qiu G. H. Su

Application of OECD THAI HM Test Results to Simulation of Hydrogen Stratification in VVER-1000 Containment with MELCOR Code

Ji（r）í Duspiva

Discussion of the Comparison of Fuel Assemblies And Associated Components Significant Advantage between AP1000 and AFA-3G fuel assembly

Li Xuesong

Experimental Performance Analysis for Cold Trap Design

M.G.Hemanath A.Ashok kumar S.Chandramouli C.Meikandamurthy G.Padmakumar K.K.Rajan B.Venkatraman P.Kalyanasundaram G.Vaidyanathan

Research on Data and Model-based Diagnostic Methods for Nuclear Power Plants

Dongxiang JIANG Chao LIU Xiao FU

Oxidation and Corrosion Behavior of a 14Cr Oxide Dispersion Strengthened Ferritic Steel Applied for Supercritical Water Reactor

Lu Liao Zhangjian Zhou Ming Li Lefu Zhang Yichen Bao

CFD Analysis of Flow Distribution at The Core Inlet of a Nuclear Pressurized Water Reactor

Ge ZHANG Yanhua YANG Hanyang GU

Sub-Channel Analysis of TRU Fuel Fabrication Coupled with Multi-Dimensional Thermal Hydraulics

T. Takata Yamaguchi K. Hishida K. Ikeda K. Itoh

Thermal Response of the HTR-10 during Loss of Forced Cooling Test without Reactor Scram

Fubing Chen Yujie Dong Yanhua Zheng Fu Li Zuoyi Zhang

Mechanical Analysis of a Test Fuel Assembly for a Reactor with Supercritical Water

P. Kremers T. Schulenberg H. Herbell

Thermal Analysis of a Test Fuel Element for a Reactor with Supercritical Water

M. Raqué A. Wank T. Schulenberg P. Hajek

Development and Implementation of Different Schemes for the Coupling of the System Code ATHLET with the 3D CFD Program ANSYS CFX

Angel Papukchiev Georg Lerchl

Prandtl Number Dependency on Transient Natural Convection in a Horizontal Enclosure of Fluid with Adiabatic Body

Jae Ryong Lee

Study on Core Melt Process for a 1000MW Reactor by External Reactor Vessel Cooling

FU Xiaoliang YANG Yanhua

Simulation of Break-up of Gas Stratification by a Vertical Jet using the GOTHIC Code

Michele Andreani Ralf Kapulla Robert Zboray