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首页> 外文期刊>Atomic Energy >REACTOR PRESSURE VESSEL COOLING SCHEME: SELECTION AND VALIDATION FOR SMALL NUCLEAR POWER PLANTS
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REACTOR PRESSURE VESSEL COOLING SCHEME: SELECTION AND VALIDATION FOR SMALL NUCLEAR POWER PLANTS

机译:反应堆压力容器冷却方案:小核电厂的选择和验证

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摘要

An analysis of existing and possible designs of high-temperature gas-cooled reactor installations has shed light on the critical elements determining the reactor's efficiency and reliability; it required determination of approaches to the development and theoretical and experimental substantiation of solutions for such critical units. Among the problems requiring a separate investigation in the development of the concept for the reactor are the selection and validation of the solutions for the cooling system of the reactor's pressure vessel, which is one of the nuclear and radiation safety barriers. The selection and validation were accomplished using modern software tools, tests, and tests and experimental studies were performed on prototypes. The proposed and substantiated, both computationally and experimentally, scheme of the low-temperature leg that cools the units of the reactor vessel that are sensitive to high temperatures made it possible to reduce the temperature gradient and increase the permissible stresses on the reactor pressure vessel.
机译:对高温气冷式反应器装置的现有和可能设计的分析在确定反应堆效率和可靠性的关键元件上具有脱光;它需要确定对这些关键单位的解决方案的开发和理论和实验证实的方法。在需要单独调查的问题中,反应堆的概念的开发是反应器压力容器冷却系统的选择和验证,这是核和辐射安全屏障之一。使用现代软件工具,测试和测试和测试和实验研究完成了选择和验证,对原型进行了实验研究。在计算和实验中提出和证实,低温腿的方案冷却对高温敏感的反应器容器单元使得可以降低温度梯度并增加反应器压力容器上的允许应力。

著录项

  • 来源
    《Atomic Energy》 |2021年第5期|256-262|共7页
  • 作者单位

    Dollezhal Res & Dev Inst Power Engn NIKIET Moscow Russia;

    Dollezhal Res & Dev Inst Power Engn NIKIET Moscow Russia;

    Dollezhal Res & Dev Inst Power Engn NIKIET Moscow Russia;

    Dollezhal Res & Dev Inst Power Engn NIKIET Moscow Russia;

    Dollezhal Res & Dev Inst Power Engn NIKIET 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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