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Comparative analysis of microstructure and reactive sites for nuclear graphite IG-110 and graphite matrix A3

机译:核石墨IG-110和石墨矩阵A3微观结构和反应性位点的比较分析

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Nuclear graphite and graphite matrix are both high-purity, fine-grain, graphitized materials designed for use in Fluoride-Salt Cooled High Temperature Reactors (FHRs), High Temperature Gas Cooled Reactors (HTGRs), and Molten Salt Reactors (MSRs). Their ability to chemisorb radioisotopes (such as tritium) and their chemical stability is dependent upon the density of reactive carbon sites (RCS), which varies among grades of graphite and changes with neutron irradiation. While nuclear graphites have been extensively characterized, much less data is available for graphite matrix. The current study performs a comparative analysis of IG-110 nuclear graphite and A3 graphite matrix, by X-ray Diffraction (XRD), Raman, and H-2 uptake at 700 degrees C with H-2 partial pressure range of 300 Pa and 22 kPa. At 10 kPa, the RCS occupied by H-2 uptake per number of carbon atoms at the edge of a crystallite, H/C-edge, is 600(300) appm for IG-110 and 2300(200) appm for A3. Prior empirical studies for nuclear graphite establish a linear relationship between H/C and C-edge/C and degree of graphitization. The present study shows that these correlations no longer hold when extrapolating to graphite matrix; the type of defects and the defect density at the crystallite surface are different between IG-110 and A3 due to differences in raw materials and manufacturing method. (C) 2019 Elsevier B.V. All rights reserved.
机译:核石墨和石墨基质均为高纯度,细粒,设计用于氟化盐冷却的高温反应器(FHRS),高温气体冷却反应器(HTGR)和熔融盐反应器(MSR)的石墨化材料。它们能够化学测量放射性同位素(例如氚)及其化学稳定性取决于反应性碳位点(RCS)的密度,其在石墨等级中变化并随着中子辐射的变化。虽然核石墨已被广泛表征,但是石墨矩阵的数据更少。目前的研究对IG-110核石墨和A3石墨基质的比较分析,通过X射线衍射(XRD),拉曼和700摄氏度的H-2摄取,H-2部分压力范围为300Pa和22 KPA。在10kPa下,在微晶的边缘处的H-2碳原子占据的RC,H / C-Edge的边缘为600(300)APPM,用于A3的IG-110和2300(200)APPM。核石墨的经验研究建立了H / C和C边/ C的线性关系以及石墨化程度。本研究表明,当外推到石墨矩阵时,这些相关性不再保持;由于原料和制造方法的差异,缺陷的类型和微晶表面的缺陷密度在IG-110和A3之间是不同的。 (c)2019 Elsevier B.v.保留所有权利。

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