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Numerical and experimental analysis of the impact of a nuclear spent fuel cask

机译:核废燃料罐影响的数值和实验分析

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摘要

This paper deals with the numerical and experimental analyses of a shell type shock absorber for a nuclear spent fuel cask. Nine-meter free drop tests performed on reduced scale models are described. The results are compared with numerical simulations performed with FEM computer codes, considering reduced scale models as well as the prototype. The paper shows the results of a similitude analysis, with which the data obtained by means of the reduced scale models can be extrapolated to the prototype. Small discrepancies were obtained using large-scale models (1:2 and 1:6), while small-scale models (1:12) did not give reliable results. A 1:9 scale model provided useful information with a less than 20% error.
机译:本文涉及核废燃料罐壳式减震器的数值和实验分析。描述了在缩小比例模型上执行的九米自由落体测试。考虑到缩小比例的模型以及原型,将结果与使用FEM计算机代码进行的数值模拟进行比较。本文显示了相似性分析的结果,通过该相似性分析,可以将通过缩减比例模型获得的数据外推到原型中。使用大型模型(1:2和1:6)可获得小的差异,而使用小型模型(1:12)则无法提供可靠的结果。 1:9比例模型提供了有用的信息,误差小于20%。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2010年第4期|706-712|共7页
  • 作者单位

    Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa, Italy;

    Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa, Italy;

    Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa, Italy;

    Department of Mechanical, Nuclear and Production Engineering (DIMNP), Pisa University, Via Diotisalvi, Pisa, Italy;

  • 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

  • 入库时间 2022-08-18 00:44:57

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