Abstract The role of soil-structure interaction (SSI) on the risk of unacceptable performance of five non-structural components of a nuclear reactor is investigated through a representative case study consisting of a pressurized-water reactor sited at Holyhead, United Kingdom. The seismic hazard at the site is defined by a 10,000 years uniform hazard spectrum, and its corresponding design response spectrum computed for a target structural performance goal of 1 × 10−5. Nine hypothetical soil profiles, with shear wave velocities ranging from 300 m/s to 1,200 m/s, are considered. Non-linear site response analyses are performed to determine the input motion at the foundation level; seismic capacity and demand of the components are computed using response-history analyses. To obtain high-confidence performance estimates from a limited number of results, Monte-Carlo simulation is used to expand the seismic demand matrix. It is shown that the probability of unacceptable performance of the reactor is highly sensitive to SSI effects. Specifically, the beneficial effects induced by SSI on the seismic performance of the reactor are limited to models sited on stiffer soil deposits (ie, Vs ≥ 900 m/s), whereas, the median probability of unacceptable performance increases for medium-to-soft deposits.

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SSI 对核反应堆抗震性能的作用：以英国核电站为例

摘要 通过由位于英国霍利黑德的压水反应堆组成的代表性案例研究，研究了土壤-结构相互作用 (SSI) 对核反应堆五个非结构部件性能不可接受的风险的作用。场地的地震危险由 10,000 年的统一危险谱定义，其相应的设计响应谱是为 1 × 10−5 的目标结构性能目标计算的。考虑了九个假设的土壤剖面，剪切波速度范围从 300 m/s 到 1,200 m/s。执行非线性场地响应分析以确定地基水平的输入运动；使用响应历史分析计算组件的抗震能力和需求。为了从有限数量的结果中获得高可信度的性能估计，Monte-Carlo 模拟用于扩展地震需求矩阵。结果表明，反应堆性能不可接受的概率对 SSI 效应高度敏感。具体而言，SSI 对反应堆抗震性能的有益影响仅限于位于较硬土壤沉积物（即 Vs ≥ 900 m/s）上的模型，而对于中软土层，不可接受性能的中值概率增加存款。