首页> 外文期刊>Nuclear Engineering and Design >Control rod drop analysis by finite element method using fluid-structure interaction for a pressurized water reactor power plant
【24h】

Control rod drop analysis by finite element method using fluid-structure interaction for a pressurized water reactor power plant

机译:压水堆动力装置流固耦合有限元法分析

获取原文
获取原文并翻译 | 示例
获取外文期刊封面目录资料

摘要

The control rod drop analysis is very important for safety analysis. For seismic and loss of coolant accident event, the control rod assemblies shall be capable of traveling from a fully withdrawn position to 90% insertion without any blockage and within specified time and displacement limits. The analysis has been executed by analytical method using in-house code. In this method, several field data are needed. These data are obtained from nuclear, thermal-hydraulic and mechanical design groups, peculiar codes, those work groups need to cooperate together.rnFollowing the enhancement of a computer and development of the multi-physics analysis code, a new method for the control rod drop analysis is proposed by finite element method. This analysis model incorporates the structure and fluid parts, termed as a fluid and structure interaction (FS1). Because a control rod is submerged inside a guide tube of a fuel assembly, the FSI boundary condition is applied. In this model, it is assumed that the fluid is incompressible laminar flow. The structures are modeled with the solid elements because there is no deformation due to the fluid flow. The analysis two-dimensional plane model is created in the analysis with considering an axi-symmetric geometry. Therefore, the proposed analysis model will be very simple and the design data from other fields will be unnecessary.rnThe analysis results are compared with those of the in-house code, which have been used for a commercial design. After validation, it is found that the present analysis gives a useful tool in the design of the control rod and fuel assembly.
机译:控制棒跌落分析对于安全性分析非常重要。对于发生地震和冷却液损失的事故,控制杆组件应能够从完全抽出的位置移动到插入的90%,且无任何阻塞,并在规定的时间和位移范围内。该分析已使用内部代码通过分析方法执行。在这种方法中,需要几个现场数据。这些数据是从核,热液压和机械设计小组,特殊的代码中获得的,这些工作小组需要一起合作。随着计算机的增强和多物理场分析代码的开发,控制杆下落的新方法用有限元方法提出了分析方法。该分析模型包含了结构和流体部分,称为流体和结构相互作用(FS1)。因为控制杆浸没在燃料组件的导管内,所以应用了FSI边界条件。在该模型中,假设流体是不可压缩的层流。使用实体元素对结构进行建模,因为不存在由于流体流动引起的变形。在分析中,考虑轴对称几何形状创建了分析二维平面模型。因此,所提出的分析模型将非常简单,并且不需要来自其他领域的设计数据。-将分析结果与已用于商业设计的内部代码进行比较。验证之后,发现本分析为控制杆和燃料组件的设计提供了有用的工具。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2009年第10期|1857-1861|共5页
  • 作者单位

    Korea Atomic Energy Research Institute, Daedukdaero 1045 Dukjin-Dong, Yusong-Ku, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, Daedukdaero 1045 Dukjin-Dong, Yusong-Ku, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, Daedukdaero 1045 Dukjin-Dong, Yusong-Ku, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, Daedukdaero 1045 Dukjin-Dong, Yusong-Ku, Daejeon 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, Daedukdaero 1045 Dukjin-Dong, Yusong-Ku, Daejeon 305-353, Republic of Korea;

  • 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

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