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活动简介

The International Topical Meeting on High Temperature Reactor Technology is the sole international conference focused on high-temperature gas-cooled reactor including heat application technology. Inaugurated in 2002 by the European High Temperature Reactor Technology Network HTR-TN at Petten, the Netherlands, successive meetings were held in Asia (Beijing, China, 2004), Africa (Johannesburg, South Africa, 2006), North America (Washington DC, USA, 2008), Europe (Prague, Czech Republic, 2010), Asia (Tokyo, Japan, 2012 and Weihai, China, 2014). The attendees included experts from research and industry and decision makers of interest including utilities, user industries, nuclear venders and governments.

HTR2016 aims to accelerate research and development on HTGR and heat application technologies, and make practical use of HTGR systems, through discussing and exchanging on the latest results and information on the above technologies and user requests as well as future perspectives and plans. This embedded topical meeting will provide a forum for sharing of peer-reviewed, full-length technical papers covering recent advances in high temperature reactor technology. Authors and presenters are invited to participate in this event to exchange ideas and knowledge.

征稿信息

征稿范围

Technical Track-1: National Research Programs and Industrial Projects

  • Specific Program and Project Development

  • Plant and Equipment Development and Construction

  • Operating Experience

  • Test facilities and Results

 

Technical Track-2: Industrial Applications and Markets

  • Design, Engineering and Testing

  • Analytical Methodology

  • Industrial Process Heat; Hydrogen Production 

  • Desalination

  • Other Applications

 

Technical Track-3: Fuel and Waste

  • Fuel Design

  • Fabrication;Safety and Qualification

  • Irradiation and PIE

  • Modeling and Simulation;

  • Waste Management

 

Technical Track-4: Materials and Components; Metallic Material Properties and Performance

  • Non-Metallic Material Properties and Performance; Corrosion at High Temperature

  • Effect of Irradiation;

  • Major Component Design (Circulators, Hot Gas Ducts, Steam Generators, Heat Exchangers, etc.

  • Modeling and Simulation

 

Technical Track-5: Reactor Physics Analysis; Nuclear Data

  • Modeling and Simulation

  • Reactor Physics Methods and Codes 

  • Fuel/Core Designs

 

Technical Track-6: Thermal-hydraulics, Structural and Multiphysics Analyses

  • Thermophysical Property Data

  • Fluid Dynamics Methods and Codes ; Heat Transfer Methods and Codes

  • Transient and Accident Analysis Methods and Codes

  • Structural Methods and Codes

  • Multi-physics Methods and Codes

  • Natural and Mixed Convection

  • Radiation Heat Transport

  • Fission and Activation Product Transport 

  • Thermal Striping and Stratification

  • Flow Induced Vibration

  • Thermal Hydraulics of Key Components; Fuel Element, Assembly and Core Designs

 

Technical Track-7: Development, Design and Engineering

  • Progress in New Generation Reactor Designs

  • Plant Dynamics and Control

  • System and Facility Design; Economic Assessment

  • Construction Methods and Experience

 

Technical Track-8: Safety and Licensing

  • Safety Design and Analysis

  • Accident Analysis and Protection

  • Seismic Analysis and Protection

  • Source Term Evaluation; Passive Safety Concepts

  • Advanced Safety Concepts

  • Licensing Strategies

  • Licensing Application and Development Status

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重要日期

  • 会议日期

    11月06日

    2016

    至

    11月10日

    2016

  • 11月10日 2016

    注册截止日期

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