全文获取类型
收费全文 | 36853篇 |
免费 | 3982篇 |
国内免费 | 2712篇 |
专业分类
电工技术 | 3622篇 |
综合类 | 2874篇 |
化学工业 | 10947篇 |
金属工艺 | 1125篇 |
机械仪表 | 1301篇 |
建筑科学 | 2278篇 |
矿业工程 | 1069篇 |
能源动力 | 1710篇 |
轻工业 | 3120篇 |
水利工程 | 929篇 |
石油天然气 | 1745篇 |
武器工业 | 250篇 |
无线电 | 2599篇 |
一般工业技术 | 2658篇 |
冶金工业 | 1207篇 |
原子能技术 | 3439篇 |
自动化技术 | 2674篇 |
出版年
2024年 | 162篇 |
2023年 | 563篇 |
2022年 | 996篇 |
2021年 | 1285篇 |
2020年 | 1279篇 |
2019年 | 1179篇 |
2018年 | 1077篇 |
2017年 | 1277篇 |
2016年 | 1490篇 |
2015年 | 1384篇 |
2014年 | 2389篇 |
2013年 | 2964篇 |
2012年 | 2593篇 |
2011年 | 2705篇 |
2010年 | 2023篇 |
2009年 | 2140篇 |
2008年 | 1893篇 |
2007年 | 2270篇 |
2006年 | 2119篇 |
2005年 | 1764篇 |
2004年 | 1463篇 |
2003年 | 1401篇 |
2002年 | 1201篇 |
2001年 | 1077篇 |
2000年 | 861篇 |
1999年 | 740篇 |
1998年 | 553篇 |
1997年 | 441篇 |
1996年 | 359篇 |
1995年 | 325篇 |
1994年 | 282篇 |
1993年 | 235篇 |
1992年 | 168篇 |
1991年 | 184篇 |
1990年 | 145篇 |
1989年 | 106篇 |
1988年 | 70篇 |
1987年 | 72篇 |
1986年 | 50篇 |
1985年 | 59篇 |
1984年 | 41篇 |
1983年 | 32篇 |
1982年 | 20篇 |
1981年 | 15篇 |
1980年 | 21篇 |
1979年 | 5篇 |
1959年 | 40篇 |
1958年 | 2篇 |
1956年 | 4篇 |
1951年 | 7篇 |
排序方式: 共有10000条查询结果,搜索用时 15 毫秒
41.
42.
网络教育平台建设的核心是教学资源库的建设,各种类型资源的快速匹配是需要频繁使用的基础功能。现有的解决方案往往使用的是BF等经典算法,匹配效率有一定的提高空间。用XML技术作为平台中各种资源描述的统一工具,通过对XML技术中DTD模式匹配方法的研究以及对模式匹配快速算法的改进,提高模式匹配的效率,从而设计出一种有效的信息模式匹配技术模型。通过仿真实验表明该模型可有效地提高网络教育平台中信息匹配的效率,进而为平台中资源的整合与模式的统一提供支持。 相似文献
43.
针对反应堆堆芯围筒热流固耦合问题,采用三维有限元法研究堆芯围筒的热变形.考察ANSYS的三维实体热单元SOLID 70,三维实体单元SOLID 45,三维表面热效应单元SURF 152和三维热-流耦合管单元FLUID 116等单元类型的特点和实用性.建立堆芯围筒、吊篮和冷却剂的温度分析有限元模型:堆芯围筒和吊篮采用SOLID 70,结构表面与冷却剂的对流传热表面采用SURF152,堆芯围筒与吊篮之间冷却剂采用FLUID 116.采用SOLID 45建立堆芯围筒有限元模型,根据得到的堆芯围筒、吊篮和冷却剂的温度场结果分析堆芯围筒热变形.结果表明,在考虑堆芯围筒及吊篮固体和流体的交叉耦合的基础上,采用三维有限元法能比较客观地模拟反应堆堆芯处的复杂运行环境. 相似文献
44.
Abstract— A contrast‐enhanced wide‐angle high‐speed polarization modulator for active‐retarder 3‐D displays is proposed. By using a double liquid‐crystal‐cell structure together with a dedicated driving scheme and an external quarter‐wave retarder, a high‐performance modulator can be realized, resulting in minimized brightness loss and low cross‐talk levels in fast‐refresh time‐multiplexed 3‐D displays. 相似文献
45.
High-field designs could reduce the cost and complexity of tokamak reactors. Moreover, the certainty of achieving required plasma performance could be increased. Strong Ohmic heating could eliminate or significantly decrease auxiliary heating power requirements and high values of nE could be obtained in modest-size plasmas. Other potential advantages are reactor operation at modest values of , capability of higher power density and wall loading, and possibility of operation with advanced fuel mixtures. Present experimental results and basic scaling relations imply that the parameterB
2a, where B is the magnetic field and a is the minor radius, may be of special importance. A superhigh-field compact ignition experiment with very high values ofB
2a (e.g.,B
2a=150 T2 m) has the potential of Ohmically heating to ignition. This short-pulse device would use inertially cooled copper plate magnets. Compact engineering test reactor and/or experimental hybrid reactor designs would use steady-state, water-cooled copper magnets and provide long-pulse operation. Design concepts are also described for demonstration/commercial reactors. These devices could use high-field superconducting magnets with 7–10 T at the plasma axis. 相似文献
46.
Conceptual fusion reactor studies over the past 10–15 yr have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points toward smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. The results of a number of recent conceptual designs of reversed-field pinch, spheromak, and tokamak fusion reactors are summarized as examples of more compact approaches. While a focus has been placed on increasing the fusion-power-core mass power density beyond the minimum economic threshold of 100–200 kWe/tonne, other means by which the overall attractiveness of fusion as a long-term energy source are also addressed.Nomenclature
a
Plasma minor radius at outboard equatorial plane (m)
-
A
Plasma aspect ratioR
T
/a
-
AC
Annual charges ($/yr)
-
b
Plasma minor radius in vertical direction (m)
-
B
Magentic field at plasma or blanket (T)
-
B
c
Magnetic field at the coil (T)
-
B
Toroidal magnetic field (T)
-
B
Poloidal magnetic field (T)
- BOP
Balance of plant
-
C
Coil
-
COE
Cost of electricity (mills/kWeh)
- CRFPR
Compact RFP reactor
- CT
Compact torus (FRC or spheromak)
-
c
FPC
Unit cost of fusion power core ($/kg)
-
DC
Direct cost ($)
- DZP
Dense Z-pinch
-
E
Escalation rate (1/yr)
-
EDC
Escalation during construction ($)
- ET
Elongated tokamak
-
F
Annual fuel charges ($/yr)
-
FC
Component of UDC not strongly dependent or FPC size ($/kWe)
- FW
First wall
-
FPC
Fusion power core
-
f
Aux
Fraction of gross electric power recirculated to BOP
-
f
1
(IC+IDC+EDC)/DC
-
f
2
(O&M + SCR + F)/AC
-
IC
Indirect cost ($)
-
IDC
Interest during construction ($)
-
I
w
Neutron first-wall loading (MW/m2)
-
i
Toroidal plasma current (MA)
-
j
Plasma current density, I/a2
-
k
B
Boltzmann constant, 1.602(10)–16 (J/keV)
- LWR
Light-water (fission) reactor
-
MPD
Mass power density 1000PE/MFPC (kWe/tonne)
-
M
N
Blanket energy multiplication of 14.1-MeV neutron energy
-
M
FPC
Mass of fusion power core (tonne)
-
n
Plasma density (m–3) or toroidal MHD mode number
-
O&M
Annual operating and maintenance cost ($/yr)
-
p
f
Plant availability factor
- PFD
Poloidal field dominated (CTs, RFP, DZP)
-
P
Construction time (yr)
- PTH
Thermal power (MWt)
-
P
E
Net electric power (1-)P
ET
(MWe)
- PET
Total gross electric power (MWe)
- pf
Fusion power (MW)
-
q
Tokamak safety factor (B
/B
gq
)(a/R
T
)
-
q
e
EngineeringQ value, 1/e
-
R
T
Major toroidal radius (m)
- RFP
Reversed-field pinch
- RPE
Reactor plant equipment (Account 22)
- S
Shield
-
SCR
Annual spare component cost ($/yr)
- SSR
Second stability region for the tokamak
- S/T/H
Stellarator/torsatron/heliotron
- ST
Spherical tokamak or spherical torus
-
T
Plasma temperature (keV)
-
TDC
Total direct cost ($)
-
TOC
Total overnight cost ($)
-
UDC
Unit direct cost,TDC/10
3
P
E
($/kWe)
-
V
p
Plasma volume (m3)
-
W
p
Plasma energy (GJ)
-
W
B
Magnetic field energy (GJ)
-
Magnetic utilization efficiency, 2nkBT/(B
2/20)
-
0
Permeability of free space, 4(10)–7 H/m
-
XE
Plasma confinement efficiency, a2/4E
-
e
Plasma energy confinement time
-
p
Overall plant efficiency, TH(1-)
-
TH
Thermal conversion efficiency
-
FPC
AverageFPC mass density (tonne/m3)
-
Plasma vertical elongation factor,b/a
-
Thickness of allFPC engineering structure surround plasma (m)
-
Total recirculating power fraction, (P
ET-P
E)/P
ET, or inverse aspect ratioa/R
T
This work was performed under the auspices of USDOE, Office of Fusion Energy. 相似文献
47.
48.
M. Rahman 《化学,工程师,技术》1975,47(17):729-729
49.
本文分析了70年代以来国际化工设备朝单系列大型化及高压力的发展趋势,以及高效能、低能耗的要求,在这个基础上介绍当前国内外化工设备新设备研制及旧设备改造的进展情况。最后提出对广州市、广东省在“八·五”期间化工设备技术的展望:乙烯设备国产化与旧设备的更新换代,进行技术改造。 相似文献
50.
烯(醚)醛一步法合成异戊二烯技术开发—基础理论研究进展 总被引:1,自引:0,他引:1
本文介绍了烯(醚)醛一步法合成异戊二烯技术开发中,基础理论研究工作的进展,其中包括化学热力学、化学动力学、再生烧炭本征动力学和扩散动力学等理论研究。并针对该反应特征进行了化学反应规律和流动传递规律的研究。建立了流化床反应器数模和流化床再生器数模,为工程技术开发提供理论依据。 相似文献