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High temperature gas reactors (HTGRs) are being considered for near term deployment in the United States under the GNEP program and farther term deployment under the Gen IV reactor design (U.S. DOE Nuclear Energy Research Advisory Committee, 2002). A common factor among current HTGR (prismatic or pebble) designs is the use of TRISO coated particle fuel. TRISO refers to the three types of coating layers (pyrolytic carbon, porous carbon, and silicon carbide) around the fuel kernel, which is both protected and contained by the layers. While there have been a number of reactors operated with coated particle fuel, and extensive amount of research has gone into designing new HTGRs, little work has been done on modeling and analysing the degradation rates of spent TRISO fuel for permanent geological disposal. An integral part of developing a spent fuel degradation modeling was to analyze the waste form without taking any consideration for engineering barriers. A basic model was developed to simulate the time to failure of spent TRISO fuel in a repository environment. Preliminary verification of the model was performed with comparison to output from a proprietary model called GARGOYLE that was also used to model degradation rates of TRISO fuel. A sensitivity study was performed to determine which fuel and repository parameters had the most significant effect on the predicted time to fuel particle failure. Results of the analysis indicate corrosion rates and thicknesses of the outer pyrolytic carbon and silicon carbide layers, along with the time dependent temperature of the spent fuel in the repository environment, have a significant effect on the time to particle failure. The thicknesses of the kernel, buffer, and IPyC layers along with the strength of the SiC layer and the pressure in the TRISO particle did not significantly alter the results from the model. It can be concluded that a better understanding of the corrosion rates of the OPyC and SiC layers, along with increasing the quality control of the OPyC and SiC layer thicknesses, can significantly reduce uncertainty in estimates of the time to failure of spent TRISO fuel in a repository environment. 相似文献
43.
《Journal of Nuclear Science and Technology》2013,50(3):393-398
The Federal Republic of Germany intends to dispose of all types of radioactive waste in deep geological formations. This waste comprises spent fuel elements, vitrified fission products, nuclear power plant operational and decommissioning waste as well as spent sealed radiation sources and miscellaneous waste originating from small waste generators. The Federal Government made a pronounced change in energy policy since 1998, the most important feature of which is the abandoning or phasing out of nuclear energy, finally set in force by the April 2002 amendment of the Atomic Energy Act. According to the new approach to waste management and disposal, further sites in various host rocks shall be investigated for their suitability. A special expert group was set up to develop repository site selection criteria and respective procedures on a scientifically sound basis. The objective of the site selection procedure is to identify—with public participation—potential disposal sites in a comprehensible and reliable way. Step by step and based on the said criteria, those areas, site regions and eventually sites shall be selected, which offer particularly favourable conditions for the later demonstration of the final site's suitability and its confirmation in a licensing procedure. 相似文献
44.
一种面向对象的软件复用框架 总被引:2,自引:0,他引:2
本文利用面向对象技术,提出了一种面向对象的软件复用框架,该框架采用面向对象的类来实现构件,为了提高构件库的组织管理效率,采用为构件库建立多个索引链等策略,构件检索采用模糊查询和详细查询的两个阶段来实现,构件集成采用基于星型拓扑结构的构件集成方法。 相似文献
45.
A simple and effective model and a GoldSim (GoldSim, 2006) template program, by which a probabilistic safety assessment of a conceptual trench-type repository for low- and intermediate level radioactive waste (LILW) disposal can be carried out under various nuclide release scenarios, have been developed. To quantify the exposure dose rates due to nuclide release from the trench and transport through the various pathways possible in the near- and far-fields of the repository system under a base case and some alternative scenarios, illustrative evaluations for a comparison among the scenarios as well as a sensitivity of shortcut pathways generated due to earthquakes on the nuclide transport are made and demonstrated. To this end, by changing the conservative base case nuclide release scenario under which all portions of the cap of the trench are failed unconditionally and immediately after a closure of the repository, a total of four other alternative scenarios were separately evaluated for the total exposure dose rates to the farming exposure group and then compared to the base case results. Among them, an earthquake scenario shows a dominant behavior almost throughout the whole time span. To see the influence of all shortcut travel pathways that are assumed to be newly generated by this earthquake scenario, their sensitivities to the exposure dose rates to the farming exposure group were also made and compared to each other. 相似文献
46.
目前大多数的视频语义概念提取研究没有考虑到视频多模态之间的关联共生特性,而在样本的标注方面采用自定义的概念进行标注,会影响语义概念提取的准确率。针对上述问题,提出结合Simfusion算法和用本体知识库标注样本的方法提取视频的语义概念,该方法根据镜头内容变化提取关键帧,在提取出镜头内容时,有效地利用镜头多模态之间的时序关联共生特性,同时运用本体知识库中的概念标注样本、训练分类器,弥补传统方法在标注样本时存在的主观、不规范等不足。实验结果表明,该方法在视频语义概念提取的研究中,有较高的准确度、可操作性强。 相似文献
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In this paper, we study the impact a heat source makes on the thermo-hydraulic behaviour of a system composed of an engineered clay barrier and a host rock, namely an argillite. We first perform a benchmark test case with code CAST3M and code ASTER. The results of the calculations are in good agreement, except for the gas pressure. Nevertheless, gas pressure does not seem to influence the saturation process, although the saturation kinetics is governed by the darcean water flow. The saturation process is accelerated when the heat source is taken into account. More precisely, this acceleration is due to dynamic viscosity increase with heating. In a second time, five other heating sources have been tested in code ASTER. Compared with the reference calculations, some give an identical response. However, the highest heating sources provoke a desaturation phenomenon because of the air pressure increase with temperature. The liquid saturation of the engineered barrier is then delayed. 相似文献
49.
Matthias Jarke Rainer Gallersdörfer Manfred A. Jeusfeld Martin Staudt Stefan Eherer 《Journal of Intelligent Information Systems》1995,4(2):167-192
Deductive object bases attempt to combine the advantages of deductive relational databases with those of object-oriented databases. We review modeling and implementation issues encountered during the development of ConceptBase, a prototype deductive object manager supporting the Telos object model. Significant features include: 1) The symmetric treatment of object-oriented, logic-oriented and graph-oriented perspectives, 2) an infinite metaclass hierarchy as a prerequisite for extensibility and schema evolution, 3) a simple yet powerful formal semantics used as the basis for implementation, 4) a client-server architecture supporting collaborative work in a wide-area setting. Several application experiences demonstrate the value of the approach especially in the field of meta data management. 相似文献
50.