全文获取类型
收费全文 | 21648篇 |
免费 | 1402篇 |
国内免费 | 495篇 |
专业分类
电工技术 | 2966篇 |
技术理论 | 1篇 |
综合类 | 1682篇 |
化学工业 | 2030篇 |
金属工艺 | 1062篇 |
机械仪表 | 2115篇 |
建筑科学 | 1510篇 |
矿业工程 | 1673篇 |
能源动力 | 512篇 |
轻工业 | 1033篇 |
水利工程 | 476篇 |
石油天然气 | 1254篇 |
武器工业 | 845篇 |
无线电 | 1823篇 |
一般工业技术 | 1019篇 |
冶金工业 | 1489篇 |
原子能技术 | 432篇 |
自动化技术 | 1623篇 |
出版年
2024年 | 78篇 |
2023年 | 178篇 |
2022年 | 356篇 |
2021年 | 528篇 |
2020年 | 531篇 |
2019年 | 282篇 |
2018年 | 235篇 |
2017年 | 391篇 |
2016年 | 536篇 |
2015年 | 612篇 |
2014年 | 1569篇 |
2013年 | 1100篇 |
2012年 | 1817篇 |
2011年 | 1727篇 |
2010年 | 1310篇 |
2009年 | 1201篇 |
2008年 | 1082篇 |
2007年 | 1536篇 |
2006年 | 1363篇 |
2005年 | 1191篇 |
2004年 | 1020篇 |
2003年 | 989篇 |
2002年 | 769篇 |
2001年 | 686篇 |
2000年 | 620篇 |
1999年 | 467篇 |
1998年 | 307篇 |
1997年 | 261篇 |
1996年 | 203篇 |
1995年 | 164篇 |
1994年 | 116篇 |
1993年 | 73篇 |
1992年 | 48篇 |
1991年 | 38篇 |
1990年 | 30篇 |
1989年 | 16篇 |
1988年 | 19篇 |
1987年 | 11篇 |
1986年 | 10篇 |
1985年 | 18篇 |
1984年 | 12篇 |
1983年 | 10篇 |
1982年 | 11篇 |
1981年 | 10篇 |
1976年 | 2篇 |
1973年 | 2篇 |
1966年 | 1篇 |
1957年 | 1篇 |
1955年 | 2篇 |
1951年 | 2篇 |
排序方式: 共有10000条查询结果,搜索用时 10 毫秒
81.
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
82.
The tokamak and tandem mirror concepts are compared with alternate confinement concepts using the criteria established in DOE/ET-0047, An Evaluation of Alternate Magnetic Fusion Concepts 1977. The concepts are evaluated and rated in each of three broad categories: confidence in physics and technology, and reactor desirability. The STARFIRE and MARS reactors are used as a basis for comparing the mainline tokamak and tandem mirror concepts with the alternate concepts evaluated in DOE/ET-0047. Two recent alternate concepts, theohmically heated toroidal experiment (OHTE) and thecompact reversed field pinch reactor (CRFPR), are also evaluated. Results indicate that the physics of the mainline tokamaks and tandem mirrors is better understood than that of most alternate concepts. Both mainline concepts rank near the middle for technology requirements, and both rank near or at the bottom when compared with the reactor desirability of alternate concepts. 相似文献
83.
TIBER II is designed to be a minimum size and cost candidate for an international Engineering Test Reactor. High-current density Nb3Sn superconducting magnets with radiation-tolerant polymide insulation is combined with a minimum thickness tungsten inbored shield and a common, external vacuum boundary to minimize the inner radial build of the tokamak core. This results in a major radius of 3 m, compared to 5 m for previous ETR designs such as INTOR, with correspondingly lower costs expected. Cyclic stress fatigue limits the number of pulses so that steady-state current drive, based on a combination of neutral beams, lower hybrid and ECH, is designed to achieve reactor-relevant nuclear testing conditions (Fluence 3MW yr/m2, rwall > 1 MW/m2 in steady state).This report is abstracted from a more complete information document UCID-20863 with numerous authors. See Ref. l for complete credits. 相似文献
84.
85.
徐亚国 《北京石油化工学院学报》2021,29(1):16-18
为了提高水下设备安装精度与工作效率,基于海上工作经验及查阅国内外相关文献,对水下设备的安装过程进行了研究,其总体过程大致分为5个阶段,即装船固定、提升操作、穿越飞溅区、深水下放、落地坐放;分析了影响水下设备安装过程的主要因素,其中水深主要影响吊放系统和设备在水下的横向偏移;波浪载荷主要应用船舶的动态响应,在设备经历穿越飞溅区阶段时对设备及缆绳造成损伤的风险较大;水下设备自身参数主要影响安装方式和安装船舶的选用。 相似文献
86.
在介绍小型材的需求与生产现状的基础上,分析了目前新建和改建小型轧机中的一些技术问题,并推荐了小型轧机生产应采用的新工艺、新技术、新设备。 相似文献
87.
城市综合管廊是现代城市建设的重要综合系统,其电气工程设计工作需要关注供电电源、接地系统、照明设计、电气设备防潮、电缆敷设等关键环节。 相似文献
88.
89.
在原有国产高线轧机基础上,经改进,如采用新型闭口式轧机,超高速机架,顶交无扭精轧机组等。为重钢高线车间进行了设计,终轧保证速度达到80m/s,使我国高线轧机国产化达到了新阶段。 相似文献
90.
地下环境中电子设备的腐蚀与防护 总被引:3,自引:0,他引:3
程环境中电子设备所承受的湿度、温度、腐蚀性气体、空气沉积物、微生物等环境应力因素及其腐蚀效应,概述总结了电子设备腐蚀机制及主要类型,并提出电子设备设计与使用中抑制腐蚀的措施. 相似文献