氢同位素在聚变堆包层结构材料中的渗透滞留行为研究

发布时间：2019-06-24 19:56

【摘要】：聚变包层以低活化钢、钒合金作为主要候选结构材料,然而这两种材料均存在高氢同位素渗透、滞留的缺点。氢同位素在包层结构材料中的渗透滞留问题直接关系到聚变堆的经济性与安全性并影响了氚自持的可行性。本论文主要借助气体驱动渗透设备(GDP)与热脱附谱仪(TDS),获得了 CLF-1钢在服役温度下的氢同位素渗透滞留参数,并进一步面向实际工况,结合高能重离子辐照装置、直线等离子体源装置以及多种微观结构、成分表征手段,针对包括高能中子辐照、阻氚涂层、等离子体暴露在内的服役环境因素对氢同位素输运的影响,系统研究了氢同位素在包层结构材料中的渗透滞留行为。首先,获得了中国ITER TBM结构材料CLF-1钢在其服役温度下的氘渗透参数,并借助3.5MeV氦离子辐照,研究了辐照损伤对氘渗透滞留行为的影响。实验结果显示CLF-1钢具有与国外F82H、EUROFER97钢接近的基本渗透参数。低剂量的氦离子辐照对氘在CLF-1钢中的渗透率与扩散系数影响极小,高剂量的氦离子辐照会降低氘渗透率、扩散系数并大大提高氘滞留总量。本研究既可以丰富CLF-1钢的基础数据库,又可以为ITER及CFETR氚输运分析提供基础数据。其次,基于HTUPS钢的文献及实验数据,提出了 Fe-Cr-Al铁素体钢作为阻氚涂层材料的可能,并对其热氧化及氘渗透行为进行了表征。经过90小时800℃空气氛围热氧化,Fe-Cr-Al表面生成了一层150nm-450nm厚以Al2O3为主要成分的氧化层,氧化层中发现了 α-Al203的存在。GDP测试结果显示氘渗透率相比CLF-1钢低2-3个数量级。为了考核辐照对热氧化Fe-Cr-Al铁素体钢的氘渗透行为的影响,利用高能金离子在氧化层中引入了辐照损伤。正电子湮没测试显示空位型缺陷的密度随辐照剂量的增加而增大。GDP测试结果显示在服役温度范围内,不同剂量的辐照损伤导致了氘渗透率的不同程度的上升。本研究为新型阻氚涂层的开发提供了参考,同时辐照损伤对于阻氚涂层材料氘渗透率的影响的研究填补了国内相关领域的空白。最后,借助MAPES平台研究了 EAST氘等离子体暴露下F82H钢、V-5Cr-5Ti氘的滞留行为,并将包层不同设计概念中钨铠甲的添加与否考虑进来,对其影响进行了表征;借助直线等离子体源研究了氦等离子体暴露对F82H钢表面微观组织的影响及随之对氢滞留行为的影响。在经历EAST氘等离子体轰击后,F82H钢的脱附谱出现了 4个释放峰,与之前的文献中利用离子注入、气氛暴露等氢同位素注入后的TDS谱图差别极大;经历同等的等离子体暴露条件后,V-4Cr-4Ti中的氘滞留量远远大于F82H钢;带涂层的F82H钢、V-5Cr-5Ti合金表面均出现了大面积的剥落,且V-5Cr-5Ti合金表面更为严重,未剥落的区域,涂层与基体界面出现大量的鼓包;添加了薄钨层的样品的F82H钢、V-5Cr-5Ti的氘滞留总量比裸样品低。在经历氦等离子体辐照后,F82H钢表面出现了一系列的奇异形貌,如迷宫状密布的富钨须状结构、密布的纳米级针孔以及截面上不同尺寸的空洞等,对其产生机理进行了探究,并研究了氦等离子体暴露对氢滞留的影响。本研究对裸包层结构材料作为包层面向等离子体材料进行了评估,并实验验证了钨与包层结构材料界面为氢同位素聚集区域,相关数据可以为聚变堆包层第一壁的设计提供参考。另外,氢同位素滞留数据,特别是经过托卡马克大装置暴露后的数据,丰富了聚变堆包层结构材料的性能数据库。
[Abstract]:The fusion cladding is used as the main candidate structural material with low activation steel and metal alloy, however, the two materials have the disadvantages of high hydrogen isotope permeation and retention. The penetration and retention of the hydrogen isotope in the cladding structure material is directly related to the economy and the safety of the fusion reactor and the feasibility of the tritium self-holding. By means of the gas-driven osmotic engine (GDP) and the thermal desorption spectrometer (TDS), the hydrogen isotope permeation retention parameters of the CLF-1 steel at the service temperature are obtained, and the high-energy heavy ion irradiation device is combined with the practical working conditions. the invention relates to a linear plasma source device and a plurality of micro-structures and component characterization means, which are used for the influence of service environmental factors including high-energy neutron irradiation, tritium coating and plasma exposure on the hydrogen isotope transport, The penetration retention behavior of the hydrogen isotope in the cladding structure is studied. First, the penetration parameters of the CLF-1 steel of the ITER TBM structure in China are obtained, and the influence of the irradiation damage on the penetration retention behavior of the CLF-1 steel is studied by means of the 3.5 MeV helium ion irradiation. The experimental results show that the CLF-1 steel has the basic penetration parameters close to the foreign F82H and EUROF97 steel. The low dose of helium ion irradiation has little effect on the permeability and diffusion coefficient in the CLF-1 steel. This study can enrich the basic database of CLF-1 steel, and can provide basic data for ITER and CFETR tritium transport analysis. Secondly, based on the literature and experimental data of HTUPS steel, the possibility of Fe-Cr-Al ferrite steel as the material of tritium-resistant coating was put forward, and its thermal oxidation and penetration behavior were characterized. On the surface of Fe-Cr-Al, an oxide layer of 150-450 nm and Al2O3 as the main component was formed on the surface of Fe-Cr-Al by thermal oxidation of an air atmosphere of 800 鈩，

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