...
首页> 外文期刊>Kerntechnik >Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
【24h】

Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals

机译:通过核反应堆容器内部压紧弹簧的挠性系数模型分析摩擦系数和限制器载荷试验

获取原文
获取原文并翻译 | 示例
           

摘要

The friction force between the contact surfaces of a reactor internal hold-down spring (HDS) and core barrel flanges can directly influence the axial stiffness of an HDS. However, friction coefficient cannot be obtained through theoretical analysis. This study performs a mathematical deduction of the physical model of an HDS. Moreover, a mathematical model of axial load P, displacement delta, and flexibility coefficient is established, and a set of test apparatuses is designed to simulate the preloading process of the HDS. According to the experimental research and theoretical analysis, P-d curves and the flexibility coefficient lambda are obtained in the loading processes of the HDS. The friction coefficient f of the M1000 HDS is further calculated as 0.224. The displacement limit load value (4,638 kN) can be obtained through a displacement limit experiment. With the friction coefficient considered, the theoretical load is 4,271 kN, which is relatively close to the experimental result. Thus, the friction coefficient exerts an influence on the displacement limit load P. The friction coefficient should be considered in the design analysis for HDS.
机译:反应堆内部压紧弹簧(HDS)和堆芯筒法兰的接触表面之间的摩擦力会直接影响HDS的轴向刚度。然而,摩擦系数不能通过理论分析获得。这项研究对HDS的物理模型进行了数学推论。此外,建立了轴向载荷P,位移增量和挠性系数的数学模型,并设计了一组测试设备来模拟HDS的预加载过程。根据实验研究和理论分析,在HDS的加载过程中获得了P-d曲线和挠性系数λ。 M1000 HDS的摩擦系数f进一步计算为0.224。位移极限载荷值(4,638 kN)可以通过位移极限实验获得。考虑到摩擦系数,理论载荷为4,271 kN,相对接近实验结果。因此,摩擦系数会对位移极限载荷P产生影响。在HDS的设计分析中应考虑摩擦系数。

著录项

  • 来源
    《Kerntechnik》 |2017年第5期|579-585|共7页
  • 作者单位

    Zhejiang Univ Technol, Coll Mech Engn, Hangzhou 310014, Zhejiang, Peoples R China;

    Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China;

    Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号