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首页> 外文期刊>International Journal of Pressure Vessels and Piping >Verification and validation of dynamic response simulation codes for BWR fuel assemblies under seismic loading
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Verification and validation of dynamic response simulation codes for BWR fuel assemblies under seismic loading

机译:地震载荷下BWR燃料组件动态响应仿真码的验证及验证

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The purpose of this study is to verify and validate two independently developed simulation codes for investigating dynamic response behaviors of fuel assemblies in a boiling water reactor (BWR) under seismic loading. The core of BWR consists of several hundreds of fuel assemblies. They are supported with both top guide and fuel support and are surrounded by coolant water. It is important to grasp their dynamic response behaviors under seismic loading for securing the structural integrity of the fuel assembly itself as well as for assessing control rod scrammability. For this evaluation of dynamic response behaviors, reliable simulation codes are required. In this study, we employ two different numerical simulation methods of acoustic fluid-structure interaction (AFSI) developed by the present authors independently. The one is a three-dimensional parallel finite element method for AFSI problems with solid elements based on a partitioned coupling approach, while the other is a finite element method of beam elements for fuel assemblies combining added mass matrix, which represents coupled inertia effects caused by coolant water. Both methods are implemented and applied to a problem of 368 fuel assemblies for verification and validation. The problem was set up based on the demonstration test performed by Nuclear Power Engineering Corporation in 1986. Both simulation results agreed well with each other, and the simulated results also agreed well with the experimental ones. In addition, we have discussed seismic response behaviors of fuel assemblies, which were not shown in the demonstration test. Finally, we conclude that the both developed simulation codes based on the proposed methods are powerful tools to grasp the behavior of huge number of fuel assemblies of BWR under seismic loading and to improve the seismic safety design of BWR core.
机译:本研究的目的是验证和验证两个独立开发的模拟代码,用于研究地震载荷下沸水反应器(BWR)中燃料组件的动态响应行为。 BWR的核心由几百款燃料组件组成。它们都是顶部导向和燃料支撑的支持,并被冷却水包围。重要的是要在地震载荷下掌握动态响应行为,以确保燃料组件本身的结构完整性以及评估控​​制杆可释放性。对于这种动态响应行为的评估,需要可靠的仿真代码。在这项研究中,我们采用了两种不同的数字仿真方法,由本作者独立开发的声学流体结构相互作用(AFSI)。该第一是基于分隔耦合方法的固体元件的AFSI问题的三维平行有限元方法,而另一个是用于组合添加的质量矩阵的燃料组件的梁元件的有限元件方法,这表示由此引起的耦合惯性效应冷却水。两种方法都实施并应用于368个燃料组件的问题,用于验证和验证。该问题是根据1986年核电工程公司执行的演示试验的建立。两种模拟结果彼此一致,模拟结果也与实验结果很好。此外,我们已经讨论了燃料组件的地震反应行为,其未在示范试验中显示。最后,我们得出结论,基于所提出的方法的两种开发的仿真代码都是强大的工具,以掌握地震载荷下的BWR燃料组件数量大量燃料组件的行为,提高BWR核心的地震安全设计。

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