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INVESTIGATION OF TAILORED SIC/SIC COMPOSITES FOR SODIUM-COOLED FAST REACTORS

机译:钠冷却快速反应器定制SiC / SiC复合材料的研究

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Increasing the sustainability and the safety of nuclear reactors require the development of new types of reactors (GEN-Ⅳ systems) which can work as breeder (producing more fuel that it consumes) and can offer the possibility of burning minor actinides to reduce the waste, such as the Sodium- (SFR) or the Gas-cooled (GFR) Fast Reactors. Therefore, there is a need to assess materials which can withstand these very harsh core conditions. In this aim, SiC/SiC composites are promising candidates thanks to their high decomposition temperature (>2000°C), low swelling and creep under irradiation and good neutron transparency. A recent CEA patent has highlighted that SiC/SiC-based hexagonal tubes would increase the resistance to melting and, as a consequence, the safety of the SFR core. In this way, techniques have been developed to manufacture a SiC/SiC hexagonal tube with given dimensions, which has a relatively low level of porosities and a pseudo-ductile mechanical behavior (tolerance to deformation). Besides, the chemical compatibility between SiC and SiC/SiC composites towards liquid sodium and its impurities (in particular oxygen) was investigated. For this purpose, two sets of experiments were conducted in the CORRONa~2 facility (CEA). On the one hand, immersions up to 2000h in an oxygen-purified ([O]<10ppm) liquid sodium heated up to the nominal temperature of a SFR (550°C) were carried out. On the other hand, oxygen was inserted in the liquid sodium to reach important oxygen quantities ([O] = 1000 ppm), well above the reference considered for incidental and transient states, to investigate the influence of this element on the SiC/SiC composites. Indeed, the SiC/SiC composites and their pyrocarbon interphase (employed to have a good linkage between the fiber and the matrix) can encounter active or passive oxidation at high temperatures. Mass assessments, SEM, XPS, X-ray tomography and tensile tests were conducted to characterize the sample properties before and after immersion. As a result, it was observed that there is no significant degradation of the material after exposure to either the oxygen-poor or -rich environments. Moreover, in some cases, an increase of the mechanical properties of SiC/SiC composites was observed.
机译:增加核反应堆的可持续性和安全性需要开发新型的反应堆(Gen-an Systems),其可以作为饲养员(产生更多的燃料,即它消耗的燃料),并且可以提供燃烧轻微的散光以减少废物的可能性,以减少浪费,如钠 - (SFR)或气体冷却(GFR)快速反应器。因此,需要评估能够承受这些非常苛刻的核心条件的材料。在此目的中,由于其高分解温度(> 2000°C),辐照和良好的中子透明度,SiC / SiC复合材料具有很有希望的候选者。最近的CEA专利突出显示SiC / SiC的六边形管将增加对熔化的抵抗力,并且因此,SFR核心的安全性。以这种方式,已经开发了技术以制造具有给定尺寸的SiC / SiC六边形管,其具有相对较低水平的孔隙率和伪延展性机械行为(耐受变形的耐受性)。此外,研究了SiC和SiC / SiC复合材料的化学相容性,朝向液体钠及其杂质(特别是氧气)。为此目的,在Corrona〜2设施(CEA)中进行两组实验。在一方面,在氧净化([O] <10ppm)液体钠中浸入到SFR(550℃)的标称温度的氧净化([O] <10ppm)液体钠中的沉浸。另一方面,将氧气插入液体钠中以达到重要氧量([O] = 1000ppm),远高于考虑偶然和瞬态状态的参考,以研究该元素对SiC / SiC复合材料的影响。实际上,SiC / SiC复合材料及其吡烃相互作用(用于在纤维和基质之间具有良好的连杆)可以在高温下遇到活性或被动氧化。进行质谱,SEM,XPS,X射线断层扫描和拉伸试验,以表征浸渍前后的样品性质。结果,观察到在暴露于贫氧或 - 中的环境之后没有显着降解材料。此外,在一些情况下,观察到SiC / SiC复合材料的力学性能的增加。

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