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DESIGN OF THE 4S REACTOR

机译:4S反应器的设计

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摘要

The Super-Safe, Small and Simple (4S) sodium cooled fast reactor plant incorporates innovative design features, such as a nonrefueling reactor, passive safety, low maintenance requirements, and inherent security. Major components such as the reflector drive mecha nisms, the electromagnetic pumps, and the double-wall tube steam generator have been optimized for efficient and safe operation. The nonrefueling reactor concept is made possible by incorporating a 30-yr refueling interval for the reflector-controlled metallic fuel core. Sodium-cooled, metallic-fueled fast reactors have a good conversion ratio due to fast neutron usage, thus extending the core life. Passive safety is achieved with redundant residual heat removal systems that function using only natural circu lation, and a metallic core with a negative reactivity coefficient. Low maintenance requirements are achieved by simplifying the design and minimizing the use of ac tive components, and by using electromagnetic pumps, which have no moving parts. The inherent security of the nuclear materials is significantly enhanced by the non refueling reactor concept and the minimal maintenance requirements. In addition, the reactor building is located below ground level, providing substantial protection against an aircraft impact and thus further enhancing the security of the design. The demonstration of key components such as the electromagnetic pumps and the steam generator is part of an ongoing testing program that has already con firmed many of the 4S engineering solutions. This paper describes the current status of design and component tests for the 4S reactor.
机译:超级安全,小型和简单(4S)钠冷却快堆工厂具有创新的设计功能,例如不加燃料的反应堆,被动安全性,低维护要求和固有安全性。反射器驱动机构,电磁泵和双壁管式蒸汽发生器等主要组件已经过优化,可实现高效安全的运行。通过为反射器控制的金属燃料芯引入30年的加油间隔,可以实现非加油反应堆概念。钠冷却的金属燃料快堆由于中子的快速使用而具有良好的转化率,从而延长了堆芯的使用寿命。通过仅使用自然循环运行的冗余余热排除系统和具有负反应系数的金属芯,可实现被动安全性。通过简化设计并最大程度地减少有源组件的使用,以及使用不带活动部件的电磁泵,可以实现较低的维护要求。不加燃料的反应堆概念和最小的维护要求大大增强了核材料的固有安全性。此外,反应堆建筑物位于地面以下,为飞机的撞击提供了重要的保护,从而进一步提高了设计的安全性。电磁泵和蒸汽发生器等关键组件的演示是正在进行的测试计划的一部分,该计划已经确定了许多4S工程解决方案。本文介绍了4S反应堆的设计和组件测试的当前状态。

著录项

  • 来源
    《Nuclear Technology》 |2012年第2期|p.201-217|共17页
  • 作者单位

    Toshiba Corporation, Advanced System Design and Engineering Department,8, Shinsugita-Cho, Isogo-Ku, Yokohama 235-8523, Japan;

    Toshiba Corporation, Advanced System Design and Engineering Department,8, Shinsugita-Cho, Isogo-Ku, Yokohama 235-8523, Japan;

    Central Research Institute of Electric Power Industry, Nuclear Technology Research Laboratory, 2-11-1, Iwado Kita, Kimae-shi, Tokyo 201-8511, Japan;

    Westinghouse Electric Company, Nuclear Services, 19239 W. Alice Court Waddell, Arizona 85355;

    Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439;

  • 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
  • 关键词

    sodium fast reactor; 4S; toshiba;

    机译:钠快堆4S;东芝;
  • 入库时间 2022-08-18 00:43:39

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