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首页> 外文期刊>Annals of nuclear energy >Dynamic impact characteristics of KN-18 SNF transport cask - Part 1: An advanced numerical simulation and validation technique
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Dynamic impact characteristics of KN-18 SNF transport cask - Part 1: An advanced numerical simulation and validation technique

机译:KN-18 SNF运输桶的动态冲击特性-第1部分:先进的数值模拟和验证技术

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摘要

Domestic and international regulations for the transportation of radioactive materials strictly prescribe the design requirements for spent nuclear fuel (SNF) transport casks. According to the applicable codes, a transport cask must withstand a free-drop impact of 9 m onto an unyielding surface and a free-drop impact of 1 m onto a mild steel bar. However, the structural performance of a transport cask is not easy to evaluate precisely because the dynamic impact characteristics of the cask, which includes impact lim-iters to absorb the impact energy, are so complex.rnIn this study, a more advanced and applicable numerical simulation method using the finite element (FE) method via the commercial FE code LS-DYNA is proposed and verified against the experimental results for a 1/3-scale model of the KN-18 SNF transport cask, recently developed in Korea. In addition, the detailed dynamic impact characteristics of the transport cask under free-drop conditions are investigated via the proposed numerical simulation method and actual drop tests to improve the accuracy and optimization of the SNF transport cask.
机译:国内外有关放射性物质运输的法规严格规定了乏核燃料(SNF)运输桶的设计要求。根据适用的规范,运输桶必须承受9 m的自由落体冲击到坚硬的表面上,以及承受1 m的自由落体冲击到软钢上。但是,运输桶的结构性能不容易精确评估,因为运输桶的动态冲击特性(包括吸收冲击能量的冲击限制剂)非常复杂。提出了使用有限元(FE)方法通过商业FE代码LS-DYNA进行模拟的方法,并针对最近在韩国开发的KN-18 SNF运输桶的1/3比例模型的实验结果进行了验证。此外,通过提出的数值模拟方法和实际跌落试验研究了运输桶在自由落体条件下的详细动态冲击特性,以提高SNF运输桶的精度和优化。

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  • 来源
    《Annals of nuclear energy》 |2010年第4期|p.546-559|共14页
  • 作者单位

    Korea Nuclear Engineering & Service Corporation, 210-2 Yangjae-dong, Seocho-gu, Seoul 137-130, Republic of Korea;

    rnKorea Nuclear Engineering & Service Corporation, 210-2 Yangjae-dong, Seocho-gu, Seoul 137-130, Republic of Korea;

    rnKorea Nuclear Engineering & Service Corporation, 210-2 Yangjae-dong, Seocho-gu, Seoul 137-130, Republic of Korea;

    Department of Aeronautical/Mechanical Design, Chungju National University, Jeungpyeong 368-903, Republic of Korea;

    Department of Architectural Engineering, Chungnam National University, Daejeon 305-764, Republic of Korea;

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