专家对WWER-1000反应堆容器因循环损伤而产生的传热传质过程对剩余寿命的影响进行了评估

V. Popov, V. Mileikovskyi, О. Tryhub
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引用次数: 0

摘要

乌克兰仍然是一个依靠核能供热和卫星供电的国家。在靠近核电站的城市,利用核电站产生的电力进行电加热是合适的。另一方面,乌克兰是世界上唯一一个发生过最严重核电站事故的国家,切尔诺贝利核电站4号机组发生在1986年4月26日晚上。乌克兰核能的另一个特点是大量的发电机组已经耗尽了项目资源,即所谓的“旧”发电机组。它们的磨损与传热传质过程的影响有关,传热传质过程导致元件的周期性热变形,从而导致循环损伤。给出了一个考虑非稳态传热传质和机械过程共同作用的专家快速评估特定反应堆容器WWER-1000剩余寿命的实例。对WWER-1000反应堆容器在危险应急模式下金属的循环(疲劳)损伤进行了详细的表达式计算。WWER-1000反应堆是前苏联最后一个最广泛和最强大的水-水核反应堆,在乌克兰核电站(npp)的15个运行动力装置中的13个上运行-扎波罗热,里夫内,赫梅利尼茨基和南乌克兰(SUNPP)。反应堆是核电厂不可缺少的重要组成部分,它决定着核电厂的安全性和资源性。鉴于乌克兰核电站机组的设计资源和调试日期,对WWER-1000船体技术状况进行快速专家评估的问题是非常相关的。当然,现代工程拥有完成这种估算所需的全套工具,从功能强大的计算机到先进的计算软件。但是现代工程的已知和不可避免的成本——复杂和耗时的建模和计算。经验表明,使用相对简化的“轻”计算方法的某种“合理”组合,使我们能够非常快速地评估WWER-1000反应堆的安全性、强度和使用寿命,并具有专家意见可接受的必要精度。该出版物以1985年10月22日的实际紧急情况和SUNPP 1号机组WWER-1000反应堆为例。由于这一紧急情况导致了该反应堆的快速冷却,因此计算了反应堆钢的循环损伤对反应堆容器强度和可靠性的影响。这个例子和对真实紧急情况的考虑表明,使用估计的专家快速评估来准确确定核反应堆建筑物等核电厂关键部件的可靠性和安全性是有效和可接受的。
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Expert express assessment of the impact of heat and mass transfer processes on the residual life of the WWER-1000 reactor vessel due to cyclic damage
Ukraine remains a country dependent on nuclear energy for both heat supply and satellite supply. In cities close to nuclear power plants, electric heating from the electricity they produce is appropriate. On the other hand, Ukraine is the only country in the world where the worst accident at a nuclear power plant occurred at the Chernobyl NPP Unit 4 on the night of April 26, 1986. Another characteristic feature of Ukraine's nuclear energy is the significant number of power units with exhausted project resources - the so-called "old" power units. Their wear is associated with the influence of heat and mass transfer processes, which lead to periodic thermal deformation of the elements, which causes cyclic damage. An example of expert rapid assessment of the residual life of a specific reactor vessel WWER-1000 is given taking into account the combined action of non-stationary heat and mass transfer and mechanical processes. A detailed express calculation of cyclic (tired) damage to the metal of the WWER-1000 reactor vessel due to the dangerous emergency mode has been performed. The WWER-1000 reactor is the last most widespread and most powerful water-water nuclear reactor of the former USSR, operated on 13 of the 15 operating power units of Ukrainian nuclear power plants (NPPs) - Zaporizhia, Rivne, Khmelnytsky and South Ukraine (SUNPP). The reactor is the most important indispensable element of a nuclear power plant, which determines its safety and resource. Given the design resource and the dates of commissioning of Ukrainian NPP units, the issue of rapid expert assessment of the technical condition of WWER-1000 hulls is quite relevant. Of course, modern engineering has the full range of tools needed to perform such estimates, from powerful computers to advanced computing software. But the known and inevitable costs of modern engineering - complex and time-consuming modeling and calculations. Experience has shown that a certain "reasonable" combination of the use of relatively simplified "light" calculation methods allows us to assess the safety, strength and service life of WWER-1000 reactors very quickly and with the necessary accuracy acceptable for expert opinion. The publication considers as an example the real emergency situation of October 22, 1985 and the WWER-1000 reactor of SUNPP Unit 1. Since this emergency situation led to rapid cooling of this reactor, the calculation of the effect of cyclic damage of reactor steel on the strength and reliability of the reactor vessel is shown. This example and the consideration of the real emergency situation demonstrates the effectiveness and acceptability of the use of estimated expert rapid assessments to accurately determine the reliability and safety of such critical elements of nuclear power plants as nuclear reactor buildings.
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