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反应堆正常运行时,吊篮组件受到冷却剂的作用而诱发振动,往往会造成吊篮及其支撑结构发生疲劳破坏或松动脱落,危及反应堆的安全。通过长期对运行中的反应堆吊篮振动特性的监测发现:随着反应堆的运行,吊篮的固有频率,特别是梁式频率会发生较大的变化,而常规吊篮模态的计算方法是无法模拟和预测该梁式频率的变化规律。针对该问题提出了在劣化支撑条件下吊篮结构模态分析的计算方法和力学模型,该方法准确模拟了不同的劣化状态下吊篮的约束边界。以国内某堆型的吊篮结构为研究对象,分别计算了在空气和静水中支撑条件劣化5%、10%、15%、20%、25%、30%、35%、40%时的振动模态,并与国外学者相关研究的试验结果进行对比,结果表明:本文提出的反应堆吊篮在劣化支撑条件下的振动模态计算方法与相关研究的试验结果趋势一致,吻合较好。因此,该计算模型是合理、可行的,能够满足工程计算分析的需求。
During the normal operation of the reactor, the components of the basket are exposed to the action of the coolant to induce vibration, which often results in fatigue damage or looseness of the basket and its supporting structure, which may endanger the safety of the reactor. Through long-term monitoring of the vibrating characteristics of the operating reactor basket, it is found that with the operation of the reactor, the natural frequency of the basket, especially the beam frequency, changes greatly. However, the calculation method of the conventional basket mode can not be calculated Simulation and prediction of the beam frequency changes. Aiming at this problem, a calculation method and a mechanical model of the basket structure modal analysis under deteriorating support conditions are proposed. The method accurately simulates the constraint boundaries of the basket under different deteriorating conditions. Taking the structure of some domestic basket as the research object, the vibration of 5%, 10%, 15%, 20%, 25%, 30%, 35% and 40% The results show that the proposed vibration mode calculation method of the reactor basket under the condition of deteriorating support has the same trend with the experimental results of the related researches, which is in good agreement. Therefore, the calculation model is reasonable and feasible to meet the needs of engineering calculation and analysis.