Seismic design, qualification, and risk assessment of nuclear safety-related vessels filled with liquid will have to consider the interaction between the vessel (tank), the contained liquid, and submerged components, if any. Seismic fluid-structure-interaction (FSI) analysis of nuclear vessels will rely on numerical models, which are required to be verified and validated. This study validates previously-verified numerical models using test data generated from earthquake-simulator experiments involving a cylindrical tank. Two solvers in LS-DYNA for FSI simulations are used for the numerical analysis: Arbitrary-Lagrangian-Eulerian (ALE) and Incompressible Computational Fluid Dynamics (ICFD). Numerical and test results are compared for responses critical to seismic design of advanced reactor vessels: hydrodynamic pressures on the tank wall, reactions at the support, and wave heights of the contained liquid. Analysis is performed for one-, two-, and three-directional seismic inputs with a range of intensity, and rocking motions. The accuracy of the numerical results and different methods for outputting wave heights are discussed. Recommendations for validation of seismic FSI numerical models of advanced reactors are provided. The validation exercise presented in this study is broadly applicable to cylindrical tanks, regardless of industry sector.

装有液体的与核安全相关的容器的抗震设计，鉴定和风险评估，必须考虑容器（容器），所容纳的液体和被淹没的组件（如果有）之间的相互作用。核容器的地震流体-结构相互作用（FSI）分析将依赖于数值模型，需要进行验证和确认。这项研究使用从涉及圆筒形储罐的地震模拟实验产生的测试数据验证了先前验证过的数值模型。LS-DYNA中用于FSI模拟的两个求解器用于数值分析：任意拉格朗日欧拉（ALE）和不可压缩计算流体动力学（ICFD）。比较了数值结果和测试结果，得出了对先进反应堆容器的抗震设计至关重要的响应：储罐壁上的流体动力压力，支撑处的反应以及所含液体的波高。对具有一定范围的强度和摇摆运动的一，二，三方向地震输入进行分析。讨论了数值结果的准确性以及输出波高的不同方法。提供了验证先进反应堆地震FSI数值模型的建议。这项研究提出的验证工作广泛适用于圆柱形储罐，而不论其行业是什么。提供了验证先进反应堆地震FSI数值模型的建议。这项研究提出的验证工作广泛适用于圆柱形储罐，而不论其行业是什么。提供了验证先进反应堆地震FSI数值模型的建议。这项研究提出的验证工作广泛适用于圆柱形储罐，而不论其行业是什么。