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101.
102.
On the mechanism of aluminum ignition in steam explosions 总被引:1,自引:0,他引:1
An available theory [Epstein, M., Fauske, H.K., 1994. A crystallization theory of underwater aluminum ignition. Nucl. Eng. Des. 146, 147–164] of the ignition of aluminum melt drops under water, which is based on the assumption that the aluminum oxide (Al2O3) drop-surface skin first appears in a metastable molten state, is compared with existing experimental data on the ignition of aluminum drops behind shock waves in water [Theofanous, T.G., Chen, X., DiPiazza, P., Epstein, M., Fauske, H.K., 1994. Ignition of aluminum droplets behind shock waves in water, Phys. Fluids 6, 3513–3515]. The predicted and measured ignition temperature of about 1770 K coincides approximately with the spontaneous nucleation temperature of supercooled liquid Al2O3 (1760 K). This suggests that the crystallization of the oxide layer represents a strong ‘barrier’ to aluminum drop ignition under water. Apparently a similar interpretation is applicable to aluminum drop ignition in gaseous oxidizing atmospheres. We conclude from the theory that the low-temperature aluminum ignitions (in the range 1100–1600 K) that have been observed during steam explosions are a consequence of the short aluminum drop oxidation times in this environment relative to the characteristic time for Al2O3 crystallization. Several aspects of the aluminum drop/shock interaction experiments besides ignition are discussed in the paper. In particular, the experiments provide strong evidence that during the course of a vapor explosion metal fragmentation occurs via a thermal mechanism at low pressure and precedes the development of a high-pressure shock. 相似文献
103.
M. Kamoshida F. Kawamura A. Sasahira T. Fukasawa T. Sawa J. Yamashita 《Progress in Nuclear Energy》2000,37(1-4):145-150
Hybrid Recycle System (HRS) is proposed as an advanced recycle system. The HRS consists of improved fluoride volatility reprocessing and vibration packing MOX fuel fabrication processing. For the former, a part of U is volatilized as hexafluoride with diluted F2 gas, and then residual U and Pu are volatilized with concentrated F2 gas. Plutonium content of the mixed fluoride gas can be adjusted as desired by controlling the U fluorination reaction in the first step. The U is highly decontaminated and the mixture gas of UF6 and PuF6 is not purified. The fluoride mixture is reacted with H2O and H2 and directly converted to the mixed oxide grain for the vibration packing. The HRS can reduce the costs of reprocessing and fuel fabrication, the amounts of radioactive wastes and the probability of Pu proliferation. 相似文献
104.
Naka R. Watanabe K. Kawarabayashi J. Uritani A. Iguchi T. Hayashi N. Kojima N. Yoshida T. Kaneko J. Takeuchi H. Kakuta T. 《IEEE transactions on nuclear science》2001,48(6):2348-2351
The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length and can obtain continuous radiation distributions. A principle of the position sensing is based on a time-of-flight technique. The monitor is sensitive to beta rays or charged particles, gamma rays, and fast neutrons. The spatial resolutions for beta-rays ( 90Sr-90Y), gamma-rays (137Cs), and D-T neutrons are 30, 37, and 13 cm, respectively. The detection efficiencies for the beta-rays, gamma-rays, and D-T neutrons are 0.11%, 1.6×10 -5% and 1.2×10-4%, respectively. The effective attenuation length of the detection efficiency is 18 m. In this paper, we describe the basic characteristics of this monitor 相似文献
105.
R. P. C. Schram K. Bakker H. Hein J. G. Boshoven R. R. van der Laan C. M. Sciolla T. Yamashita Ch. Hellwig F. Ingold R. Conrad S. Casalta 《Progress in Nuclear Energy》2001,38(3-4):259-262
In the plutonium incineration experiment, named ‘Once-Through-Then-Out’ (OTTO), that is being prepared by JAERI, PSI and NRG, the use of highly stable inert matrices will be examined. The inert matrices MgAl2O4 spinel and ZrO2 are insoluble in nitric acid and are considered as good storage media for final disposal. These inert matrices will be used in this experiment, which is representative for an OTTO scenario. A total of 7 Pu-containing targets were prepared for an irradiation in the High Flux Reactor in Petten. The objective of the irradiation is to reach a very high Pu-burnup. The main parameters to be studied are stability under irradiation, swelling, fission gas release and chemical interactions in the fuel. Four targets will be equipped with thermocouples for on-line monitoring of central temperature. Four of the targets contain MgAl2O4 as an inert matrix, 2 targets contain ZrO2 and one target contains mixed-oxide (MOX) fuel for reference purposes. The fissile plutonium concentration is 0.32–0.44 g cm−3. Both particle-dispersed fuel and homogeneous dispersions were fabricated in order to test the effect of the size of the fissile inclusions. The design of the experiment and the fabrication of the samples are discussed. 相似文献
106.
T. Yamashita H. Akie Y. Nakano K. Kuramoto N. Nitani T. Nakamura 《Progress in Nuclear Energy》2001,38(3-4):327-330
Intention of the ROX-LWR system research is to provide an option for utilization or disposition of surplus plutonium. Researches on inert matrix materials and irradiation performance shows that the most favorable candidate for the ROX fuel is a particle dispersed fuel where small particles consisted of yttria stabilized zirconia, PuO2 and some additives are homogeneously dispersed in spinel matrix. Reactor safety analyses show that the ROX fueled PWR core has nearly the same performability as the existing UO2 fueled PWR under both reactivity initiated accidents and loss of coolant accidents. 相似文献
107.
A. V. Beznosov V. A. Kir'yanov T. A. Bokova N. E. Fiseiskii S. S. Pinaev V. N. Zakhvatov 《Atomic Energy》2001,90(1):12-16
The goal of the work reflected in this paper is to investigate the mass transfer of lead from the coolant surface in the gaseous cavities of the cooling loop of a BREST-OD-300 reactor. The theoretical and experimental investigations show that the amount of lead evaporating from the free surfaces of the first loop of the reactor is negligible.The results of this work are the recommendations that filters should be placed at locations where the pipelines of the gas system, located outside the reactor block, are connected to the reactor cover, because of the possibility of aerosols – dust-like impurities from other sources with mass flow several times greater than the rate of evaporation of lead in the unit – entering the gas system. 2 figures, 7 references. 相似文献
108.
Summary It has been found that the method of moisture determination introduced by Parsons and Holmberg, in which water is evolved
from the sample and absorbed on CaCl2, is absolute and is applicable to all types of oils and fats, except those containing residual solvent. It is particularly
suited for the determination of very low percentages of moisture in oils and fats.
Of the methods recommended by the A.O.C.S. for the determination of moisture and volatile in oils and fats, the vacuum oven
was found to be the most accurate, except on high-fatty-acid coconut oil.
The hot-plate method gave the highest moisture results when the test was conducted according to the procedure outlined in
the methods of the A.O.C.S. When first traces of smoking were observed under a strong beam of concentrated light, resulting
moistures approached those obtained by the vacuum oven.
Moisture results obtained by the air oven, if corrected for peroxide absorption, approach those of the vacuum oven.
The percent of residual solvent in extracted soyabean oil, independent of moisture, may be accurately determined by adsorption
of solvent vapor on activated charcoal. 相似文献
109.
110.