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排序方式: 共有884条查询结果,搜索用时 31 毫秒
1.
为了能随时在实验室及野外施工现场对动圈检波器进行参数测试,给出了基于直流激励法原理、以Cyclone Ⅲ EP3C40F780和ADS1282等为硬件的动圈检波器参数测试仪的设计方案。该测试仪利用现场可编程门阵列(FPGA)作为主控制器,FPGA将接收到来自ADS1282采集处理的数据通过网口传给PC,软件对传来的数据进行处理可以得到动圈检波器的阻尼比、自然频率、灵敏度等7个参数,并实时保存。用该测试仪对LGT20D系列检波器进行了测试,结果表明该测试仪对小阻尼检波器参数测试有较高的准确性。 相似文献
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为了提高激光跟踪仪的跟踪精度,改善激光跟踪仪性能,根据测量光斑在PSD上的坐标可实现光斑位移测量的原理,研究了提高微位移测量精度的方法,设计出一种由PSD传感器、ADS8556模数转换器和TMS320F28335数字信号处理器构成的高性能微位移测量系统.该系统在硬件设计中引入二阶有源低通滤波器消除了部分噪声干扰;在软件设计中通过误差补偿和数字滤波进一步提高了数据可靠性.加入抗干扰设计后,获得的二维坐标波动量峰峰值均在6μm以内.实验表明,该系统可获得高精度的光斑坐标,为激光跟踪仪精密跟踪奠定良好基础. 相似文献
4.
设计了一种HART协议通信接口。给出了具体的软硬件设计,采用HART专业低功耗调制解调芯片AD5700实现了HART信号的调制、解调与载波监听,利用AD5421电流环数模转换器实现了4m A-20m A电流输出及变送器的二线制传输,达到了变送器与上位机进行HART远程通信的目的。 相似文献
5.
与传统加速器驱动次临界系统(ADS)采用金属靶作为散裂中子靶的设计不同,加速器驱动次临界熔盐堆(AD-MSRs)采用靶堆一体的设计,直接使用燃料熔盐作为散裂中子靶。由于熔盐靶的中子学性能直接影响AD MSRs的能量放大系数、核废物的嬗变和核燃料增殖的效率,所以本研究基于MCNPX程序,详细计算了高能质子轰击氟盐和氯盐两种熔盐靶产生的散裂中子产额、散裂中子能谱、能量沉积分布以及散裂产物等中子学性能,并与液态Pb和铅铋共熔体(LBE)两种液态金属靶进行了对比。计算结果表明,熔盐靶在散裂中子产额上与液态金属靶有一定的差距,但熔盐靶内能量沉积分布的梯度较小,更有利于靶区的热量导出。与液态Pb和LBE靶相比,熔盐靶的散裂产物中包含更多的气体以及高质量数的α发射体核素。 相似文献
6.
Xian Zeng Qinsheng Wang Xie Meng Zhao Chen Yong Zhang 《Journal of Nuclear Science and Technology》2020,57(5):590-598
ABSTRACTOxygen measurement and control system is critical for minimizing corrosion in nuclear systems. Oxygen measurement and control tools use lead-bismuth eutectic (LBE) and pure lead as a coolant or as a spallation target. Oxygen can be supplied by either gas phase (H2O or O2) or solid phase (PbO dissolution); thus, oxygen control includes both gas phase and solid phase methods. This article focuses on oxygen concentration measurement and control of lead-bismuth eutectic in a small, static experimental facility. This facility was developed for oxygen sensor calibration and gas/solid phase control systems test programs. The oxygen sensor with Nano Cu/Cu2O closely the Nernstian behavior down to 195°C; the oxygen sensor measurement accuracy satisfied the requirements of subsequent experiments. The gas phase control system (verified according to different type of mass transfer, such as air, H2O, gas injection, and coverage) and the solid phase control system were very successful in small experimental devices. Accurate oxygen concentration control was achieved with both the gas and solid phase control systems. 相似文献
7.
Cheol Ho Pyeon Masao Yamanaka Akito Oizumi Masahiro Fukushima Go Chiba Kenichi Watanabe 《Journal of Nuclear Science and Technology》2019,56(8):684-689
This study demonstrates, for the first time, the principle of nuclear transmutation of minor actinide (MA) by the accelerator-driven system (ADS) through the injection of high-energy neutrons into the subcritical core at the Kyoto University Critical Assembly. The main objective of the experiments is to confirm fission reactions of neptunium-237 (237Np) and americium-241 (241Am), and capture reactions of 237Np. Subcritical irradiation of 237Np and 241Am foils is conducted in a hard spectrum core with the use of the back-to-back fission chamber that obtains simultaneously two signals from specially installed test (237Np or 241Am) and reference (uranium-235) foils. The first nuclear transmutation of 237Np and 241Am by ADS soundly implemented by combining the subcritical core and the 100 MeV proton accelerator, and the use of a lead-bismuth target, is conclusively demonstrated through the experimental results of fission and capture reaction events. 相似文献
8.
《International Journal of Hydrogen Energy》2019,44(3):1392-1408
Hydrogen, rather than oil, must be produced in volumes not provided by the currently employed methods. In this work, two high-temperature hydrogen production methods coupled with an advanced nuclear system are presented. A new design of a pebble-bed accelerator nuclear-driven system called TADSEA (Transmutation Advanced Device for Sustainable Energy Applications) was chosen because of the advantages in transmutation and safety. A detailed flowsheet of the high-temperature electrolysis process coupled to TADSEA through a Brayton gas cycle was developed using chemical process simulation software: Aspen HYSYS®. It is obtained 0.1627 kg/s of hydrogen with the model with optimized operating conditions, resulting in an overall process efficiency of 34.51%, a value in the range of results reported by other authors. A conceptual design of a plant using the iodine-sulfur thermochemical water splitting cycle was carried out producing 5.66e-2 kg/s and electric energy in cogeneration. The overall efficiency was calculated performing an energy balance resulting in 22.56%. A brief hydrogen production cost estimation was performed for both methods obtaining 5.96$/kg for the sulfur-iodine (SI) and 4.8 $/kg for the high-temperature electrolysis (HTE) process. 相似文献
9.
电力系统监控产品中,模拟量数据流程是影响系统性能的重要因素。文中提出了一种基于ADSP中SPORT及IDMA的模拟量输入接口。实际应用表明,该方法可以简化数据流程,提高系统效率。 相似文献
10.
Advanced nuclear water reactors rely on containment behaviour in realization of some of their passive safety functions. Steam condensation on containment walls, where non-condensable gas effects are significant, is an important feature of the new passive containment concepts, like the AP600/1000 ones.In this work the international reactor innovative and secure (IRIS) was taken as reference, and the relevant condensation phenomena involved within its containment were investigated with different computational tools. In particular, IRIS containment response to a small break LOCA (SBLOCA) was calculated with GOTHIC and RELAP5 codes. A simplified model of IRIS containment drywell was implemented with RELAP5 according to a sliced approach, based on the two-pipe-with-junction concept, while it was addressed with GOTHIC using several modelling options, regarding both heat transfer correlations and volume and thermal structure nodalization. The influence on containment behaviour prediction was investigated in terms of drywell temperature and pressure response, heat transfer coefficient (HTC) and steam volume fraction distribution, and internal recirculating mass flow rate. The objective of the paper is to preliminarily compare the capability of the two codes in modelling of the same postulated accident, thus to check the results obtained with RELAP5, when applied in a situation not covered by its validation matrix (comprising SBLOCA and to some extent LBLOCA transients, but not explicitly the modelling of large dry containment volumes).The option to include or not droplets in fluid mass flow discharged to the containment was the most influencing parameter for GOTHIC simulations. Despite some drawbacks, due, e.g. to a marked overestimation of internal natural recirculation, RELAP5 confirmed its capability to satisfactorily model the basic processes in IRIS containment following SBLOCA. 相似文献