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REGULATORY ASPECTS OF AGING MANAGEMENT IN ARGENTINA

机译:阿根廷老龄化管理的监管方面

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摘要

The nuclear power plant Atucha I is in operation from 1974. It is a power station of the type PHWR with a power of 357 MW and with a temperature of operation of 262℃. The nucleus this formed at the present time by 252 fuels channels. The fuels are of 37 bars, one structural and 36 fuels bars of natural uranium with 0,85% enrichment and of a longitude of 6,18 meters. This nucleus this inside a vessel of a steel 22NiMoCr37 and built with badges of different cast. For the characteristics of their design the top of the reactor cannot be retired without a high radiological and economic cost. This takes to that took the decision of placing the samples of the surveillance program in the bottom part of the fuels channels. Initially they were placed two set of test of samples that they should be extracted to 50% and the end of the life of the power plant. This situation takes to design a program of irradiations in experimental reactors, we irradiates material in SCK-CEN in Belgium, with an acceleration of 700 times, showing the material a similar behaviour to the VAK. We irradiates material in Lovissa, Finland, with a factor of advance of 24 times if being necessary it will be irradiated in the reactor RA1, in Argentina. Everything with the purpose of knows the current state of the recipient. In this work this irradiations are analysed, being compared the results and the importance of this knowledge was commented for the design of the surveillance programme of Atucha II.
机译:核电站Atucha I于1974年开始运行。它是PHWR类型的电站,功率为357 MW,工作温度为262℃。目前由252个燃料通道形成的核。燃料为37巴,一种结构铀和36根天然铀燃料,浓缩度为0.85%,经度为6,18米。该核位于钢22NiMoCr37的容器内,并用不同铸件的徽章制成。由于其设计的特点,如果没有高昂的放射学和经济成本,就不能淘汰反应堆的顶部。为此,决定将监视程序的样本放置在燃料通道的底部。最初,他们接受了两组样品测试,应将其提取至50%,并终止电厂的使用寿命。这种情况需要设计一个实验堆中的辐照程序,我们以700倍的加速度辐照比利时SCK-CEN中的材料,显示出与VAK相似的性能。我们在芬兰的洛维萨(Lovissa)辐射材料,如果需要的话,可以提前24倍进行辐射,该材料将在阿根廷的RA1反应堆中辐射。一切目的都是知道接收者的当前状态。在这项工作中,分析了这种辐射,并比较了结果,并评论了此知识对于设计Atucha II监视程序的重要性。

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