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Characterisation of high temperature refractory ceramics for nuclear applications

机译:核应用的高温耐火陶瓷的特征

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The ternary oxide ceramic system UO_2-ZrO_2-FeO is a refractory system that is of great relevance to the nuclear industry as it represents one of the main systems resulting from the interaction of the Zircaloy cladding, the UO_2 fuel and the structural elements of a nuclear reactor. It is particularly the high temperature properties that require investigation; that is, when substantial overheating of the nuclear core occurs and interactions can lead to its degradation, melting and result in a severe nuclear accident. There has been much work on the UO_2-ZrO_2 system and also on the ternary system with FeO but there is still a need to examine 2 further aspects; firstly the effect of sub-oxidized systems, the UO_2-Zr and FeO-Zr systems, and secondly the effect of Fe/Zr or Fe/U ratios on the melting point of the U-Zr-Fe oxide system. Samples of UO_2-Zr and UO_2-ZrO_2-FeO were fabricated at ITU and then characterized by optical microscopy (OM) and X-ray diffraction to determine the ceramic's structure and verify the composition. Thereafter the samples are to be melted by laser flash heating and their liquidus and solidus temperatures determined by pyrometry. This programme is currently ongoing. The frozen samples, after testing, were then sectioned, polished and the molten zone micro-analytically examined by OM & SEM-EDS in order to determine its structure and composition and to compare with the existing phase diagrams. Examples of results from these systems will be given. Finally, a reacted Zr-FeO thermite mixture was examined, which had been used to generate high temperatures during tests of reactor melt-concrete interactions. The aim was to assess the reaction and estimate the heat generation from this novel technique. These results allow verification or improvement of the phase diagram and are of primary importance as input to models used to predict materials interactions in a severe nuclear accident.
机译:三元氧化物陶瓷系统UO_2-ZrO_2-FeO的是耐火系统,该系统有很大关联的核工业,因为它代表从Zircaloy合金包层的相互作用,所述UO_2燃料和核的结构元件所产生的主系统中的一个反应堆。特别是需要调查的高温性质;也就是说,当核核心发生大量过热时,相互作用会导致其降解,融化和导致严重的核事故。在UO_2-ZRO_2系统上以及FEO的三元系统上有很多工作,但仍然需要检查2个进一步的方面;首先亚氧化系统的效果,UO_2锆和FeO - 锆系统,和其次的Fe / Zr的或Fe / U比在U-Zr系Fe氧化物系统的熔点的影响。在ITU制造UO_2-Zr和UO_2-ZrO_2-Feo的样品,然后通过光学显微镜(OM)和X射线衍射来表征以确定陶瓷的结构并验证组合物。此后,样品将通过激光闪蒸加热及其液相液体和通过热测定确定的固体温度熔化。该计划目前正在进行中。然后将冷冻样品在测试后,抛光和熔融区通过OM和SEM-ED进行微观分析检查,以便确定其结构和组成,并与现有相图进行比较。将给出这些系统的结果的例子。最后,检查了反应的Zr-Feo热质混合物,用于在反应器熔体混凝土相互作用的测试期间产生高温。目的是评估反应并估计这种新技术的发热。这些结果允许验证或改进相图,并且作为用于预测严重核事故中的材料相互作用的模型的输入主要重要。

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