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THE METHOD FOR STRUCTURAL RELIABILITY ESTIMATION OF THE HEAT EXCHANGER TUBES OF STEAM GENERATOR OF WWER NPPs

机译:污水核电厂蒸汽发生器换热管结构可靠度的估算方法

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After the replacement due to the well known problem of weld seam #111 the steam generators (SG) of the Ukrainian WWER-1000 type nuclear power plants (NPP) have been in operation for almost 25 years. So now, the main practical problem related to the SG is the leakage/breaking of heat exchanger tubes (HET). If the leakage criterion is not satisfied the NPP Unit has to be stopped until the corresponding HET is plugged, which leads to unexpected huge financial losses. Every year at least 12.5% of the SG HETs are controlled by eddy current inspection, after which some of the HETs are plugged according to the appropriate plugging criteria (in most cases - 65% loss of tube wall thickness). Thus, every SG has its own statistics of plugging. From the practical point of view the Utility is interested in the following questions: whether the failure of the HET happens during the normal operation mode (NOM) up to the next NPP stop or not; what is the probability of this event; what is the defect growth rate? Answers on these questions could give us the opportunity to increase the effectiveness of the HET in-service inspection and to improve the plugging criterion. A simple statistically-based method for HET integrity assessment is proposed. The method based on an exponent distribution law and HET plugging statistics of specific SG, taking into account defect growth. Based on the history of the tubes plugging (year of operation versus quantity of pluggings) the three statistical parameters inherent to this specific SG have to be found: initial number of defects, parameter of the exponential distribution (initial defect size) and the defect growth rate. The developed method was used for the prediction of HET leak/break number for all Ukrainian WWER-1000 SG. It is shown that for those SG which has less than 2% HET pluggings the accumulated pluggings as of the end of the next year of NOM will not exceed this value. Based on the Ukrainian history of WWER-1000 SG operation the database of HET plugging is presented. This method is also used for justification of pressure reduction of periodic hydrostatic test (HT) for primary circuit of WWER-1000 and WWER-440 NPPs from 24.5 MPa to 20.3 MPa and from 19.1 MPa to 15.7 MPa, correspondingly. To justify a reduction of the HT pressure, a quantitative, risk-informed assessment of HT effectiveness has been performed with taking into account the HT pressures change. The HET failure probability is calculated as the proportion of defects which exceed critical sizes for NOM and HT. Limit load models are used for the determination of the critical defects size. The variation of reliability is calculated as the difference between fracture probability during NOM after HT at routine and reduced pressures. It is shown that HT pressure reduction does not practically increase the fracture probability during operation, and satisfies the criteria of risk change.
机译:由于众所周知的#111焊缝问题,更换后,乌克兰WWER-1000型核电厂(NPP)的蒸汽发生器(SG)运转了将近25年。因此,现在与SG有关的主要实际问题是热交换器管(HET)的泄漏/损坏。如果不满足泄漏标准,则必须停止NPP装置,直到堵塞相应的HET,这会导致意外的巨大财务损失。每年至少有12.5%的SG HET通过涡流检查进行控制,然后根据适当的堵塞标准(在大多数情况下-管壁厚度损失65%)对一些HET进行堵塞。因此,每个SG都有其自己的堵塞统计信息。从实用的角度来看,公用事业公司对以下问题感兴趣:HET的故障是否发生在正常运行模式(NOM)直至下一个NPP停止之间;此事件的可能性是多少;缺陷增长率是多少?对这些问题的回答可以使我们有机会提高HET在役检查的有效性并改善堵塞标准。提出了一种简单的基于统计的HET完整性评估方法。该方法基于指数分布规律和特定SG的HET堵塞统计,并考虑了缺陷的增长。根据管道堵塞的历史(运行年限与堵塞数量),必须找到该特定SG固有的三个统计参数:缺陷的初始数量,指数分布的参数(初始缺陷尺寸)和缺陷的增长速度。所开发的方法用于预测所有乌克兰WWER-1000 SG的HET泄漏/断裂数。结果表明,对于那些HET堵塞率低于2%的SG,截至明年NOM年底的累积堵塞率将不会超过该值。根据乌克兰的WWER-1000 SG运行历史,介绍了HET堵塞的数据库。此方法也可用于证明WWER-1000和WWER-440 NPP一次回路的定期静水压测试(HT)的压力分别从24.5 MPa降低到20.3 MPa和从19.1 MPa降低到15.7 MPa。为了证明降低HT压力的合理性,已在考虑HT压力变化的情况下对HT有效性进行了定量的,风险告知的评估。 HET失效概率的计算方法是:缺陷的比例超过了NOM和HT的临界尺寸。极限载荷模型用于确定关键缺陷的大小。可靠性的变化计算为常规温度下HT后NOM期间的断裂概率与减压之间的差。结果表明,HT减压实际上并没有增加手术过程中的破裂几率,并且满足了风险变化的标准。

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