共查询到20条相似文献,搜索用时 156 毫秒
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聚变发电反应堆双冷液态锂铅包层模块结构设计与分析 总被引:9,自引:8,他引:1
给出聚变发电反应堆FDS Ⅱ模块式液态锂铅包层(DLL)结构方案,以低活化马氏体(RAFM)钢为结构材料,采用液态金属LiPb作为增殖材料和冷却剂,使用碳化硅流道插件作为电绝缘和热绝缘。包层的设计特点体现在:从增殖区、冷却剂流道、屏蔽包层、母管、机械连接、维修装配等几个方面全局考虑包层设计,结构布置完整;独有的“”形隔板设计使氦气冷却回路容易实现,增殖流道简单,可简化制造工艺,提高可靠性。同其他液态锂铅包层相比,DLL包层在冷却剂系统、制造、装配上可成就较高的可行性。 相似文献
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聚变驱动次临界堆概念设计研究 总被引:43,自引:27,他引:16
吴宜灿 柯严 郑善良 汪卫华 储德林 黄群英 刘晓平 许德政 王红艳 黄德所 朱晓翔 高纯静 李静惊 陈义学 吴斌 汪太平 柏云清 章毛连 刘松林 罗月童 刘萍 李春京 李强 童莉莉 翁晓毅 吴磊 王祥科 FDS课题组 《核科学与工程》2004,24(1):72-80
在深入分析相关领域研究发展状况的基础上,提出一个可实现核废料嬗变、可裂变重金属核燃料和氚核燃料增殖、产能等多种功能的次临界反应堆概念。概念有托卡马克实验装置参数适量外推的等离子体物理和技术水平的聚变堆芯、高压He气/液态LiPb双冷却系统嬗变包层。介绍了系统基本概况和参考结构形式,阐述了系统聚变等离子体物理学、包层中子物理学和包层热工水力学设计的基本原则和主要工程约束限制条件,指出系统相关的安全和潜在环境影响问题,给出典型的参考设计参数。 相似文献
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包层是聚变反应堆能量转换和提取的关键部件,聚变高温制氢堆(FDS-Ⅲ)高温液态铅锂包层(HTL)中采用创新型多层插件(MFCI)技术,由SiC_f/SiC组成的流道插件使液态铅锂实现了1 000℃左右出口温度,从而达到更高的热电转换效率和制氢能力。液态金属磁流体动力学效应MHD效应是HTL包层的重点问题之一。本文以高温包层结构为参考,采用FDS团队自主开发的磁流体动力学与热工水力学耦合模拟软件MTC,对高哈特曼数下典型多层插件流道内的液态铅锂MHD流动特性进行了数值模拟,分析了不同插件电导率对流道之间电磁耦合现象的影响。 相似文献
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中国液态锂铅包层材料研究进展 总被引:2,自引:0,他引:2
黄群英 李春京 李艳芬 刘少军 宋勇 彭蕾 章毛连 朱志强 高胜 郭智慧 王永亮 吴宜灿 周新贵 万发荣 单以银 郁金南 朱升云 张品源 杨建锋 李合琴 巨新 室贺健夫 长坂琢也 大贯惣明 FDS团队 《原子能科学技术》2007,41(Z1):397-406
液态锂铅包层是国际上普遍关注和最有发展潜力的聚变堆包层概念设计之一,而包层材料是液态锂铅包层的核心问题之一.目前,液态锂铅包层普遍选用低活化铁素体/马氏体钢(RAFM钢)作为结构材料,液态锂铅作为中子倍增剂及氚增殖剂.另外,部分设计采用了耐高温、电绝缘流道插件作为功能材料,以降低磁流体动力学效应及提高冷却剂出口温度(高于700℃).为适应液态包层的发展需求,中国科学院等离子体物理研究所FDS团队联合国内外相关研究单位,进行了具有中国自主知识产权的中国低活化马氏体钢(CLAM钢)及液态锂铅包层功能材料研发,并开展了锂铅热对流及强迫对流回路的设计、研制及腐蚀实验研究,以研究液态金属锂铅的流动特性及其与结构和功能材料的相容性.同时建立了聚变堆材料数据库平台,为促进中国聚变堆液态包层及材料技术的研究和发展提供数据支持. 相似文献
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本文对液态金属 Li 流过托卡马克工程试验增殖堆自冷包层的磁流体动力学(MHD)压降进行了分析,讨论了内侧包层有无裂变、燃料元件的形式、包层能量倍增因子 M 及第一壁冷却孔道宽度对包层总压降的影响,从 MHD 流动分析的观点,为中子学、结构和热工水力设计提出了设计要求。 相似文献
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氧势对快堆不锈钢包壳管腐蚀行为的影响 总被引:1,自引:0,他引:1
通过堆外模拟试验,研究了国产316-Ti不锈钢包壳管在4种氧势下对FCCI(燃料包壳化学相互作用)和FPLME(裂变产物液态金属脆化效应)的敏感性。结果表明包壳管腐蚀特征与氧势密切相关。当氧势低于Cr在不锈钢中的氧化阈值,包壳管内壁无明显侵蚀;当氧势超过Cr在不锈钢中的氧化阈值很多时,包壳管微观侵蚀形貌是基体氧化侵蚀与晶间侵蚀(IGA)的混和。随氧势增加,晶间侵蚀深度减小,氧化侵蚀变严重。在与超化学计量混合氧化物燃料对应的高氧势下,同时发生基体氧化侵蚀,晶间侵蚀和剥离性侵蚀,侵蚀区呈“溃疡状”,由富Cr/贫Ni和富Ni/贫Cr层交替组成。 相似文献
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金属基弥散燃料元件在特殊工况下会发生表面起泡失效。燃料颗粒开裂是金属基体开裂的前提条件,只有当金属基体开裂后元件才会发生表面起泡。燃料颗粒开裂后,裂纹宽度和塑性区长度等裂纹特征决定了金属基体开裂行为。基于弹塑性断裂力学和应力平衡条件,建立了基于弥散燃料颗粒开裂的金属基体裂纹特征模型。计算结果表明:裂纹张开位移随退火温度和燃耗深度的升高而增加;裂纹尖端塑性区长度主要与退火温度相关。裂纹张开位移和塑性区长度的计算结果与实验数据均符合较好,验证了金属基体裂纹特征模型的有效性。 相似文献
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D. Gorse T. Auger I. Serre A. Gessi C. Fazio F. Di Gabriele G. Coen M. Serrano 《Journal of Nuclear Materials》2011,415(3):284-283
In this paper, the tensile, fatigue and creep properties of the Ferritic/Martensitic (F/M) steel T91 and of the Austenitic Stainless (AS) Steel 316L in lead-bismuth eutectic (LBE) or lead, obtained in the different organizations participating to the EUROTRANS-DEMETRA project are reviewed. The results show a remarkable consistency, referring to the variety of metallurgical and surface state conditions studied. Liquid Metal Embrittlement (LME) effects are shown, remarkable on heat-treated hardened T91 and also on corroded T91 after long-term exposure to low oxygen containing Liquid Metal (LM), but hardly visible on passive or oxidized smooth T91 specimens. For T91, the ductility trough was estimated, starting just above the melting point of the embrittler (TM,E = 123.5 °C for LBE, 327 °C for lead) with the ductility recovery found at 425 °C. LME effects are weaker on 316L AS steel. Liquid Metal Assisted Creep (LMAC) effects are reported for the T91/LBE system at 550 °C, and for the T91/lead system at 525 °C. Today, if the study of the LME effects on T91 and 316L in LBE or lead can be considered well documented, in contrast, complementary investigations are necessary in order to quantify the LMAC effects in these systems, and determine rigorously the threshold creep conditions. 相似文献
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Metal coatings of Ti are vapor-deposited (200 A/day) in MACROTOR and MICROTOR during low temperature H2-discharge cleaning and operated far away from the gettering threshold for plasma impurity control. Several methods of analysis (X-ray diffraction, ESCA, AES, SEM) show that after several months of deposition two major effects have an impact on the coating: (a) formation of a porous microstructure which enhances H2,-gas trapping: (b) formation of Ti-hydride of a 100 Å crystallite size and with large microstrain present. Both effects are responsible for a mechanically and chemically unstable first wall. H/D-exchange and H-retention are affected most by the existing wall condition. These difficulties may be avoided by using a hot (≈400°C) liner. 相似文献
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《Fusion Engineering and Design》2014,89(12):3149-3158
The development of advanced fusion reactors like DEMO will have various challenges in materials and fabrication. The vacuum vessel is important part of the fusion reactor. The double walled design for vacuum vessel with thicker stainless steel material (40–60 mm) has been proposed in the advanced fusion reactors like ITER. Different welding techniques will have to be used for such vacuum vessel development. The required mechanical, structural and other properties of stainless steels have to be maintained in these joining processes of components of various shapes and sizes in the form of plates, ribs, shells, etc. The present paper reports characterization of welding joints of SS316L plates with higher thicknesses like 40 mm and 60 mm, prepared using multi-pass Tungsten Inert Gas (TIG) welding process. The weld quality has been evaluated with non-destructive tests by X-ray radiography and ultrasonic methods. The mechanical properties like tensile, bend tests, Vickers hardness and impact fracture tests have been carried out for the weld samples. Tensile property test results indicate sound weld joints with efficiencies over 100%. Hardening was observed in the weld zone in non-uniform manner. Macro and microstructure studies have been carried out for Base Metal (BM), Heat Affected Zone (HAZ) and Weld Zone (WZ). Scanning Electron Microscopy (SEM) analysis carried out for the impact fractured specimens show ductile fracture. The microstructural study and ferrite number data indicate the presence of high content of delta ferrite in the weld zone as compared to the delta ferrite in base metal. 相似文献
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Y. K. Park T. Kishimoto M. Takai 《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》1997,130(1-4):534-538
A metal-silicide wiring structure with submicron lateral feature size was analyzed successfully by a nuclear microprobe with a Liquid Metal Ion Source (LMIS). A minimum beam spot size of less than 80 nm at a current of 30 pA with a 300 keV Be2+ beam was used. The lateral distribution of WSix at submicron level was resolved using RBS mapping and tomographic imaging. The localized silicidation behavior between WSix on Si and on SiO2 was compared by microbeam RBS measurement. 相似文献
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G.O. Amolo J.D. Comins S.R. Naidoo S.H. Connell M.J. Witcomb T.E. Derry 《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》2006,250(1-2):233-237
The optical effects of implantation of lithium niobate crystals with 100 keV Ag+ and 8 MeV Au3+ ions with fluences of 1 × 1017 ions/cm2 have been investigated. Metal nanoparticle formation has been studied as a function of annealing temperature, and the resulting optical extinction curves have been simulated by the Mie theory in the small particle limit. Transmission electron microscopy (TEM) has provided direct evidence for the MNP sizes allowing comparison with the calculated results. A TEM study of an X-cut sample implanted with Ag+ ions show that the implanted region is partially amorphised. The differences in the temperature of Au colloid development in X- and Y-cut faces of the lithium niobate crystal are attributed to restoration of crystallinity as a result of annealing. 相似文献