首页> 外文会议>International conference on structural mechanics in reactor technology >A STUDY ON DETERMINATION OF VIBRATORY STRESSES AND MODAL STRESS VECTORS REQUIRED FOR QUALIFYING COMPLEX PIPING IN NUCLEAR POWER PLANTS.
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A STUDY ON DETERMINATION OF VIBRATORY STRESSES AND MODAL STRESS VECTORS REQUIRED FOR QUALIFYING COMPLEX PIPING IN NUCLEAR POWER PLANTS.

机译:确定核电厂复杂管道所需的振动应力和模态应力矢量的研究。

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A great deal of effort is put in qualifying piping for vibration in various systems of nuclear power plants. Like many critical components, piping is also required to perform specific function in shutting down a reactor to safe shut down condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. During the design stage of generation 3 reactors, ASME brought out guidelines to assess vibration levels of applicable piping system for pre-operational qualification. The guideline recommends test methods, test intervals, parameters to be measured and evaluated, acceptance criteria and corrective actions if required. The guidelines classify piping vibration into steady state and transient condition. Under each condition, the guide recommends rules for assessing piping vibration in three levels in increasing order of sophistication. The lowest level is based on visual evaluation backed with judgment and experience of similar type. The middle level is based on vibration measurement on given locations. The highest level is based on monitoring vibration with sophisticated devices to accurately determine vibratory stresses in the pipe. The third level is rigorous method to be carried out on the portion of piping which exhibits vibration response that cannot be characterized by simple piping modes. In nuclear plants, where one of the key objective is to maintain minimum fluid inventory in the system, piping are very densely laid and are designed to cater for multiple types of loads besides the conventional thermal hydraulic loads. Besides, there are number of locations in the plant where the laid piping is not accessible during the entire life time of the plant. All such lines need to be qualified by detail monitoring using sophisticated devices. The test carried for qualification should be sufficiently specific to the condition to which the piping shall be experiencing in operation. Such a test requires that the modal displacements and natural frequencies of the piping system be determined from the test. It also requires modal analysis of the piping system be performed yielding analytically determined natural frequencies and mode shapes and modal stress vectors corresponding to the mode shape vectors. The analysis and test results are correlated to obtain Modal Response Factor which can be used to determine actual state of stress in the piping due to the measured modal displacement. The correlation between the results should confirm the validity of the analysis and should indicate that the analytical results are conservative. The paper describes correlative analysis carried out between analytical and experimental results of a typical three dimensional piping section. The pipe was extensively instrumented with sensors to measure vibration, strain and pressure fluctuation in the flow through the pipe. By applying bending moments, the stress vectors of the representative analytical model are obtained which is then multiplied with the modal response factor, the ratio of test modal displacement and analytical modal displacement. This product then gives the actual stress vector developed in the test. The stress vector so obtained is compared with the experimental stress vector obtained from the strain measurement. Thus the procedure given for rigorous evaluation of piping vibration as per ASME O&M code has been verified.
机译:在核动力系统各种系统的振动管道方面付出了巨大的努力。像许多关键组件一样,还要求管道系统在将反应堆关闭至安全关闭条件,维持安全关闭条件或减轻事故后果方面执行特定功能。在第3代反应堆的设计阶段,ASME提出了指南,以评估适用管道系统的振动水平,以进行运行前鉴定。该指南建议测试方法,测试间隔,要测量和评估的参数,验收标准以及必要时采取的纠正措施。该准则将管道振动分为稳态和瞬态两种。在每种情况下,指南都建议以复杂程度从高到低的三个级别评估管道振动的规则。最低级别是基于具有类似类型的判断和经验的视觉评估。中间级别基于给定位置上的振动测量。最高水平是基于使用复杂设备监控振动以准确确定管道中的振动应力的结果。第三级是对显示出振动响应的管道部分执行的严格方法,而简单的管道模式无法对其进行表征。在核电站中,其主要目标之一是保持系统中的最低流体库存,因此,管道铺设得非常密集,并且设计成除了传统的热液压载荷外,还可以满足多种载荷类型。此外,工厂中有很多位置在工厂的整个使用寿命期间都无法接近铺设的管道。所有这些生产线都需要通过使用精密设备的详细监视进行鉴定。进行资格鉴定的测试应充分针对管道在运行中所处的条件。这种测试要求根据测试确定管道系统的模态位移和固有频率。它还要求对管道系统进行模态分析,以产生分析确定的固有频率和模态形状以及与模态形状向量相对应的模态应力向量。分析和测试结果相关联,以获取模态响应因子,该模态响应因子可用于确定由于测得的模态位移而引起的管道中应力的实际状态。结果之间的相关性应确认分析的有效性,并应表明分析结果是保守的。本文介绍了在典型的三维管道截面的分析结果与实验结果之间进行的相关分析。该管道广泛地装有传感器,以测量通过管道的流量中的振动,应变和压力波动。通过施加弯矩,获得代表性分析模型的应力矢量,然后将其乘以模态响应因子,测试模态位移与分析模态位移之比。然后,该乘积给出测试中开发的实际应力矢量。将如此获得的应力向量与从应变测量获得的实验应力向量进行比较。因此,已经验证了根据ASME O&M规范对管道振动进行严格评估的程序。

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