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Development and Application of a Comprehensive Model of a Lead-cooled Fast Reactor Using the FAST Code System

机译:FAST代码系统的铅冷快堆综合模型的开发与应用

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摘要

The purpose of this work was to develop a comprehensive model of a lead-cooled fast reactor and to apply it to the transient analysis of this reactor. The executive branch of the European Union is pursuing several ideas for advanced reactors, including a design called the European Lead-cooled System (ELSY). This design is being developed within the frame of the Lead-cooled European Advanced DEmonstration Reactor (LEADER) project. The FAST Reactors Group at the Paul Scherrer Institut has been at the forefront of fast reactor research in general and has developed a code capable of analyzing the behavior of the European Commission's new design ideas in-depth. This study used the group's code and previous experience with ELSY to develop this model.
机译:这项工作的目的是开发铅冷却快堆的综合模型并将其应用于该反应堆的瞬态分析。欧盟的行政部门正在为先进反应堆寻求多种构想,其中包括一种称为欧洲铅冷却系统(ELSY)的设计。该设计正在铅冷却的欧洲先进示范反应堆(LEADER)项目的框架内进行开发。总体而言,Paul Scherrer研究所的FAST反应堆小组一直处于快速反应堆研究的最前沿,并已开发出能够深入分析欧盟委员会新设计思想的行为的代码。这项研究使用了小组的代码和以前在ELSY方面的经验来开发此模型。

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  • 来源
    《Transactions of the American nuclear society》 |2011年第2011期|p.699-700|共2页
  • 作者单位

    Department of Nuclear Engineering, Texas A&M University, 129 Zachry Engineering Center, MS 3133 TAMU, College Station, TX, 77843-3133;

    Laboratory for Reactor Physics and Systems Behaviour, Paul Scherrer Institut, 5232 Villigen PSI,Switzerland;

    Department of Nuclear Engineering, Texas A&M University, 129 Zachry Engineering Center, MS 3133 TAMU, College Station, TX, 77843-3133;

    Department of Nuclear Engineering, Texas A&M University, 129 Zachry Engineering Center, MS 3133 TAMU, College Station, TX, 77843-3133;

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  • 正文语种 eng
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