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首页> 外文会议>Material Degradation and Related Managerial Issues at Nuclear Power Plants >INTEGRATED SURVEILLANCE SPECIMEN PROGRAM FOR WWER-1000/V-320 REACTOR PRESSURE VESSELS
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INTEGRATED SURVEILLANCE SPECIMEN PROGRAM FOR WWER-1000/V-320 REACTOR PRESSURE VESSELS

机译：WWER-1000 / V-320反应堆压力容器的集成监控样本程序

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Surveillance specimen programs play an important role in reactor pressure vessel lifetimeassessment as they should monitor changes in pressure vessel materials mainly their irradiation embrittlement. Standard surveillance programs in WWER-1000/V-320 reactor pressure vessels have some deficiencies resulting from their design - nonuniformity of neutron field and even within individual specimen sets, large gradient in neutron flux between specimens and containers, lack of neutron monitors in most of containers and no suitable temperature monitors. Moreover, location of surveillance specimens does not assure similar conditions as the beltline region of reactor pressure vessels. Thus, Modified surveillance program for WWER-1000/V-320C type reactors was designed and realized in two units of NPP Temelin, Czech Republic. In this program, large flat type containers are located on inner wall of reactor pressure vessel in the beltline region that assures their practically identical irradiation conditions with critical vessel materials. These containers with inner dimensions of 210x300 mm have two layers of specimens; using inserts (10x10x14 mm) instead of fully Charpy size specimens allows irradiation of materials from several pressure vessels at once in one container. Irradiation of these archive materials together with the IAEA reference steel JRQ (of ASTM A 533-B type) and reference steel VVER-1000 will allow to compare irradiation embrittlement of these materials and to obtain more reliable and objective results as no reliable predictive formulae exist up to no due to a higher content of nickel in welds. Irradiation of specimens from cladding region will help in the evaluation of resistance of pressure vessels against PTS regimes.
机译：监视标本程序在反应堆压力容器寿命评估中起着重要作用，因为它们应监视压力容器材料的变化，主要是辐射脆性。 WWER-1000 / V-320反应堆压力容器中的标准监视程序由于其设计而存在一些缺陷-中子场甚至在单个样本集中的不均匀，样本和容器之间的中子通量梯度很大，在大多数情况下缺乏中子监测器容器，没有合适的温度监控器。而且，监视标本的位置不能保证与反应堆压力容器的安全带区域相类似的条件。因此，在捷克共和国的NPP Temelin的两个机组中设计并实现了WWER-1000 / V-320C型反应堆的改进监视程序。在该程序中，大型扁平型容器位于反应堆压力容器内带线区域的内壁上，以确保它们在关键容器材料的照射条件下几乎相同。这些内部尺寸为210x300 mm的容器具有两层样品；使用插入物（10x10x14 mm）代替完全夏比（Charpy）尺寸的样本，可以在一个容器中一次照射来自多个压力容器的材料。将这些存档材料与IAEA参考钢JRQ（ASTM A 533-B型）和参考钢VVER-1000一起进行辐照，将可以比较这些材料的辐照脆性，并获得更可靠和客观的结果，因为不存在可靠的预测公式由于焊缝中镍含量较高，最高可达零。从包层区域辐照样品将有助于评估压力容器对PTS制度的抵抗力。

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