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Determination of the Containment Lifetime Characteristics as a Problem of Controlling the Life Cycle of NPP with VVER-1000

机译:使用VVER-1000控制NPP生命周期的问题来确定安全壳的寿命特性

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摘要

A systems approach to evaluating the service life of the reinforced, prestressed, concrete, containment shell of an NPP with VVER-1000 is examined. The main steps in evaluating the technical condition and remaining service life of its structural units are described. An additional 30-year period of operation of the containment shell of the No. 1 unit of the Kalininskaya NPP and the Nos. 2 and 3 units of the Balakovo NPP is determined on the basis of these investigations.
机译:研究了一种系统方法,该方法可评估带有VVER-1000的NPP的钢筋混凝土,预应力混凝土,安全壳的使用寿命。描述了评估其结构单元的技术条件和剩余使用寿命的主要步骤。在这些调查的基础上,确定了Kalininskaya核电厂1号机组和Balakovo核电厂2号和3号机组安全壳的另外30年运行期限。

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  • 来源
    《Atomic Energy》 |2016年第6期|380-383|共4页
  • 作者单位

    All Russia Res Inst Operat Nucl Power Plants VNII, Moscow, Russia;

    All Russia Res Inst Operat Nucl Power Plants VNII, Moscow, Russia;

    All Russia Res Inst Operat Nucl Power Plants VNII, Moscow, Russia;

    All Russia Res Inst Operat Nucl Power Plants VNII, Moscow, Russia;

    Moscow State Univ Civil Engn MGSU, Moscow, Russia;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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  • 入库时间 2022-08-18 00:38:48

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