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11.
ITER过渡馈线辅助支撑结构设计及传热计算   总被引:2,自引:1,他引:1  
过渡馈线系统是为ITER磁体系统提供能量、制冷剂、进行测量诊断等服务的子系统。本工作对过渡馈线直线段内部辅助支撑和S弯箱内部辅助支撑等进行了设计,并借助ANSYS有限元分析软件[JP2]对过渡馈线直线段内管由辅助支撑引起的传导热进行了分析。结果表明,辅助支撑结构的设计是合理的。  相似文献   
12.
托卡马克HT-7U低温超导磁体的绝缘系统   总被引:2,自引:0,他引:2  
主要介绍低温超导托卡马克HT-7U中磁体的绝缘结构,绝缘材料的特性,绝缘结构形成的工艺,绝缘层的电性能和力学性能等。  相似文献   
13.
核聚变装置放电真空室材料的要求和发展   总被引:4,自引:1,他引:3  
通过回顾托马克构核聚变实验装置的发展历程和放电真空室及内部部件材料的运用历史,联系近些年国内外一些托马克装置的最新实验结果,对不锈钢、钛合金、纤维增强的复合材料在放电真空室上的应用进行展望,为未来核聚变实验装置的工程设计和材料选择提供了依据。  相似文献   
14.
国际热核聚变实验堆(ITER)超导电流传输线导体的内部电缆体由超导股线和纯铜股线经多级绞缆后复合而成,相对柔软。在传统复合材料理论的基础上,对ITER超导电流传输线导体等效弹性模量进行理论预测:预测一,只考虑电缆体外的不锈钢导管、双绝缘和双屏蔽层;预测二,忽略柔性电缆体的影响,但考虑其内部氦管;预测三,假设电缆体呈各向同性,弹性模量取1~10GPa;预测四,利用均匀化理论分析电缆体的等效弹性模量,复合材料损伤理论分析超导电缆与中心氦管之间、电缆复合体和不锈钢导管之间界面情况。预测值与参考实验值进行比较证实,预测四较符合实际情况,电缆体对整个超导电流传输线导体等效弹性模量的影响较小。  相似文献   
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16.
管内电缆导体(CICC),是目前大型低温超导磁体的首选导体。随着超导技术的发展,CICC在大型超导核聚变实验装置及超导储能磁体中的应用具有不可比拟的优越性。为降低导体成本而提出了在CICC中采用的超导股线配以纯铜股线的设计方案,开展含纯铜股线CICC稳定性机理及实验的研究,并开发CICC优化设计软件,对CICC在高科技术中的应用意义重大。  相似文献   
17.
为了简化低温超导托卡马克HT-7U极向场线圈真空压力浸渍的模具设计和制造,降低成本和节约时间,采用袋模工艺,本文主要介绍袋模的构成,材料的选用,并通过小样实验和等截面试样实验探索HT-7U极向场磁体线圈的绝缘层真空压力浸渍的袋模工艺的可行性。  相似文献   
18.
Vacuum vessel of the HT-7U is a fully welded toroidal structure with a noncircularcross-section nested in the bore of the TF coils. According to the requirement of the physicsdesign, sixteen horizontal ports on outboard mid-plane and thirty-two vertical ports on the topand bottom are designed for diagnostics, plasma heating, current driving, vacuum pumping andgas puffing. Bellows on these port necks are used for flexible components to absorb the relativedisplacement in radial and vertical directions due to external load, thermal expansion or contrac-tion and assembly tolerance, and also used for isolation of mechanical vibration. For the supportsystem of vacuum vessel it should be not only strong enough to withstand forces acting on thevessel interior components and the vessel itself due to the dead weight and electromagnetic inter-actions during plasma disruption, but also sufficiently flexible to be suited to thermal expansionduring baking. In order to solve this contradiction a new kind of low rigid s  相似文献   
19.
EAST (experimental advanced superconducting tokamak) is an advanced steadystate plasma physics experimental device, which is being constructed as the Chinese National Nuclear Fusion Research Project. During the plasma operation the vacuum vessel as one of the key component will withstand the electromagnetic force due to the plasma disruption, the Halo current and the toroidal field coil quench, the pressure of boride water and the thermal load due to 250℃ baking by pressurized nitrogen gas. In this paper a report of the static and dynamic mechanical analyses of the vacuum vessel is made. Firstly the applied loads on the vacuum vessel were given and the static stress distribution under the gravitational loads, the pressure loads, the electromagnetic loads and thermal loads were investigated. Then a series of primary dynamic, buckling and fatigue life analyses were performed to predict the structure's dynamic behavior. A seismic analysis was also conducted.  相似文献   
20.
The Procedure for Assembling the EAST Tokamak   总被引:1,自引:0,他引:1  
Due to the complicated constitution and high precision requirements of the EAST superconducting tokamak, a meticulous assembling procedure and measurement scheme must be established. The big size and mass of the EAST machine's components and complicated configuration with tight installation tolerances call for a highly careful assembling procedure. The assembling procedure consists of three main sub-procedures for the assembling of the base, of the tori of the VV, the vacuum vessel TS and the TF, and of the peripheral parts respectively. Before the assembly, a reference framework has been set up by means of an industrial measurement system with reference fiducial targets fixed on the wall of the test hall. In this paper, the assembling procedure is described in detail, the survey control system of the assembly is discussed, and progress in the assembly work is also reported.  相似文献   
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