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Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
召开年:
2003
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1.
NSTX TF joint failure and re-design
机译:
NSTX TF关节失效并重新设计
作者:
Neumeyer C.
;
Brooks A.
;
Chrzanowski J.
;
Dudek L.
;
Heitzenroeder P.
;
Kalish M.
;
Williams M.
;
Zatz I.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
plasma toroidal confinement;
electromagnets;
fusion reactor design;
fusion reactor materials;
coils;
Tokamak devices;
NSTX;
toroidal field coil design;
National Spherical Torus Experiment;
electrical joint;
radial flags;
inner leg bundle;
structural design problems;
2.
Optimal shape of electrodes for high performance of inertial electrostatic confinement fusion
机译:
电极的最佳形状,可实现高性能的惯性静电约束聚变
作者:
Tanaka R.
;
Osawa H.
;
Tabata T.
;
Ishibashi T.
;
Ohnishi M.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
anodes;
cathodes;
fusion reactors;
plasma inertial confinement;
glow discharges;
electrodes;
inertial electrostatic confinement fusion;
ion production;
anode;
hollow cathode;
concentric spheres;
glow discharge;
spherical center;
fusion reactions;
accelerated ions;
background neutrals;
current feed-through;
negative high voltage;
spherical symmetry;
optimal shapes;
fast ion lifetime;
ellipsoid;
ion bombardment;
neutron production;
3.
Optimizing porous media microstructure characteristics for high heat flux application
机译:
优化多孔介质的微观结构特性,以实现高热通量应用
作者:
Pulsifer J.E.
;
Raffray A.R.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
helium;
porous materials;
coolants;
flow through porous media;
heat transfer;
fusion reactor materials;
tailored porous media microstructure;
MERLOT model;
heat transfer coefficients;
pressure drop;
gas coolants;
helium;
porous flow model;
energy-transfer rate;
open-porosity tailored-media;
He;
4.
Penetration of rotating magnetic field and its effects on electron confinement in field-reversed configuration
机译:
反向磁场中旋转磁场的穿透及其对电子约束的影响
作者:
Adachi H.
;
Osawa H.
;
Ohnishi M.
;
Ishida A.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
reversed field pinch;
plasma magnetohydrodynamics;
plasma theory;
rotating magnetic field;
electron confinement;
electron motion equation;
infinite long field-reversed configuration;
electron trajectories;
radial gradient;
radial electric field;
azimuthal direction;
5.
Performance characteristics of an inertial-electrostatic confinement fusion device with magnetron discharge
机译:
磁控放电惯性静电约束聚变装置的性能特征
作者:
Masuda K.
;
Yoshikawa K.
;
Mizutani T.
;
Takamatsu T.
;
Imoto M.
;
Nagasaki K.
;
Toku H.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
fusion reactors;
plasma inertial confinement;
plasma electrostatic waves;
plasma sources;
magnetrons;
glow discharges;
plasma transport processes;
cathodes;
inertial-electrostatic confinement fusion device;
magnetron discharge;
ion source;
fusion reaction rate;
grounded vacuum chamber;
central transparent cathode;
magnetron-glow hybrid discharge;
discharge voltage;
current;
gas pressure;
neutron yield;
fusion reaction;
6.
Performance evaluation of cyanate ester resin
机译:
氰酸酯树脂的性能评估
作者:
Voss G.
;
Fabian P.
;
Feucht S.
;
Harte M.
;
Terry C.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
electromagnets;
epoxy insulation;
impregnated insulation;
adhesion;
fracture toughness;
fracture toughness testing;
tensile strength;
shear strength;
compressive strength;
fusion reactor materials;
cyanate ester resin;
epoxy resin systems;
vacuum impregnation;
electromagnets;
mechanical strength;
failure mechanism;
adhesion;
copper interface;
cohesion;
thermomechanical performance;
materials testing;
70 degC;
7.
Practical experiences with the 6 gyrotron system on the DIII-D tokamak
机译:
在DIII-D托卡马克上使用6旋流器系统的实践经验
作者:
Lohr J.
;
Cary W.P.
;
Gorelov Y.A.
;
Grunloh H.J.
;
Kajiwara K.
;
Peavy J.J.
;
Ponce D.
;
Tooker J.
;
Callis R.W.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
gyrotrons;
plasma radiofrequency heating;
fusion reactor design;
Tokamak devices;
plasma toroidal confinement;
tetrodes;
waveguides;
cooling;
calorimetry;
DIII-D tokamak;
tetrode rectifier power supply;
modulator power supply;
regulator power supply;
CPI gyrotrons;
dual parallel tetrode;
Gycom tubes;
windowless evacuated transmission lines;
gyrotron instability;
high voltage circuit instability;
gyrotron conditioning;
RF beam forming;
waveguide coupling;
output window vacuum seals;
material control;
launcher mechanics;
launcher diagnosis;
polarizer mechanics;
dummy loads;
power measurements;
polarization measurements;
cooling;
calorimetry;
operating controls;
110 GHz;
1 MW;
80 percent;
5 MW;
2 s;
3 MW;
5 s;
8.
Progress on RD and design work for the ITER toroidal field coils
机译:
ITER环形场线圈的研发和设计工作的进展
作者:
Sborchia C.
;
Fillunger H.
;
Maix R.
;
Salpietro E.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
superconducting coils;
ITER toroidal field coil design;
ITER toroidal field coil manufacturing;
RD work;
toroidal field model coil;
TF coil cases;
cables;
insulation systems;
structural materials;
superconducting strands;
manufacturing techniques;
winding;
electrical joints;
European RD results;
9.
RD progress for the ITER vacuum pumping system
机译:
ITER真空泵系统的研发进展
作者:
Day Ch.
;
Antipenkov A.
;
Gross S.
;
Haas H.
;
Hauer V.
;
Mack A.
;
Murdoch D.K.
;
Wykes M.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
cryopumping;
plasma beam injection heating;
cryostats;
RD progress;
ITER vacuum pumping system;
torus exhaust gas;
neutral beam injectors;
cryostat;
mechanical forepump trains;
overview;
TIMO test bed;
scale model;
torus cryosorption pump;
operational times;
coolant flows;
gas flows;
robust technique;
10.
Recent activities on the design of the ITER deuterium/tritium fuel cycle
机译:
国际热核实验堆氘/ tri燃料循环设计的近期活动
作者:
Glugla M.
;
Antipenkov A.
;
Bekris N.
;
Caldwell-Nichols C.
;
Cristescu I.
;
Cristescu I.R.
;
Day Ch.
;
Doerr L.
;
Gross S.
;
Haas H.
;
Janeschitz G.
;
Laesser R.
;
Mack A.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
deuterium;
tritium handling;
Tokamak devices;
plasma toroidal confinement;
fusion reactor fuel;
fusion reactor design;
exhaust systems;
isotope separation;
cryopumping;
leak detection;
ITER deuterium/tritium fuel cycle design;
Task Force Fuel Cycle;
fuel cycle system manufacture;
fuel cycle system assembly;
analytical system;
storage system;
delivery system;
tokamak exhaust processing system;
isotope separation system;
water detritiation system;
Tritium Laboratory Karlsruhe;
ITER effluent reduction;
procurement packages;
neutral beam injectors;
cryostat;
pump trains;
leak localization technique;
TIMO facility;
cryopump tests;
DT;
11.
Recent advancements in the design of the LHCD system for ITER
机译:
用于ITER的LHCD系统设计的最新进展
作者:
Mirizzi F.
;
Bibet P.
;
Kuzikov S.
;
Portafaix C.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
plasma radiofrequency heating;
plasma transport processes;
Tokamak devices;
plasma toroidal confinement;
plasma sources;
circular waveguides;
rectangular waveguides;
fusion reactor materials;
plasma instability;
plasma filled waveguides;
fusion reactor design;
LHCD system;
ITER;
EDA phase;
RF power;
passive active multijunction;
microwave components;
output rectangular waveguides;
RF sources;
circular waveguides;
main transmission line;
PAM launcher;
mode filters;
ceramic windows;
vacuum vessel;
TE mode;
5 GHz;
20 MW;
12.
Recent developments in alternatives to CAMAC for data acquisition at DIII-D
机译:
用于DIII-D数据采集的CAMAC替代品的最新发展
作者:
Kellman D.H.
;
Campbell G.L.
;
Perron J.R.
;
Piglowski D.A.
;
Austin M.E.
;
McKee G.R.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
data acquisition;
fusion reactor instrumentation;
CAMAC;
analogue-digital conversion;
Tokamak devices;
plasma toroidal confinement;
data acquisition hardware;
CAMAC platform;
modern alternative hardware;
compact-PCI platform standards;
rack-mount computers;
data acquisition boards;
digitizers;
Ethernet connectivity;
analog-to-digital converters;
control circuitry;
firmware;
memory;
transfer waveform data;
triggers;
clocks;
operational parameters;
DIII-D acquisition database;
serial loop highways;
data transfer;
CAMAC systems;
printed circuit manufacture;
high channel count;
memory density;
cost savings;
personal computer industry;
13.
Reliability estimates for oxygen monitors
机译:
氧气监测仪的可靠性估算
作者:
Cadwallader L.C.
;
Petersen P.I.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
oxygen;
fusion reactor instrumentation;
reliability;
Tokamak devices;
fusion reactor safety;
gas sensors;
occupational safety;
reliability estimates;
oxygen monitor failure;
spurious alarm;
DIII-D fusion facility;
gas storage;
cryogenic systems;
gaseous nitrogen;
gaseous helium;
cryogenic nitrogen;
cryogenic helium;
personnel safety assessment;
DIII-D Trouble Report database;
monitor faults;
O/sub 2/;
N;
He;
14.
Remote participation technologies in the EFDA Laboratories - status and prospects
机译:
EFDA实验室中的远程参与技术-现状与前景
作者:
Schmidt V.
;
How J.A.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
fusion reactor operation;
reviews;
teleconferencing;
fusion reactor design;
fusion reactor instrumentation;
EFDA Laboratories;
remote participation technologies;
European Fusion Development Agreement;
overview;
remote data access;
remote computer access;
teleconferencing;
computer network;
joint scientific exploitation;
MDSplus;
multiexperiment data access;
videoconferencing;
remote control room participation;
network monitoring;
RP work;
15.
Safety issues of beryllium use in IFE power plants
机译:
IFE发电厂中使用铍的安全问题
作者:
Reyes S.
;
Cadwallader L.C.
;
Gomez del Rio J.
;
Latkowski J.F.
;
Sanz J.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
fusion reactor safety;
fusion reactor design;
beryllium;
natural radioactivity hazards;
fusion reactor targets;
nuclear facility regulation;
fusion reactor operation;
safety assessment;
beryllium;
inertial fusion energy power plant designs;
safety issue;
environmental issue;
SE assessment;
mercury;
lead;
potential hohlraum materials;
radiological consequence;
toxicological consequence;
accidental release;
chemical safety requirements;
molten salt flibe;
Li/sub 2/BeF/sub 4/;
IFE liquid-wall chamber;
target designs;
safety hazards;
chemical toxicity;
DOE regulations;
potential accident scenarios;
Be concentration limits;
public protection;
safety standards;
Be exposures;
chemical hazards;
fusion power plants;
16.
Selection of bounding events for ITER safety analysis
机译:
为国际热核实验堆安全性分析选择边界事件
作者:
Taylor N.P.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
fusion reactor safety;
Tokamak devices;
plasma toroidal confinement;
failure analysis;
bounding event selection;
ITER safety analysis;
postulated accident scenarios;
systematic accident identification;
failure mode analysis;
failure effect analysis;
postulated initiating events;
potential impacts table;
plant states;
ITER tokamak;
17.
Simulation studies of the protection system for the superconducting coils of Helias Stellarator Fusion Reactor
机译:
Helias Stellarator聚变反应堆超导线圈保护系统的仿真研究
作者:
Wieczorek A.
;
Harmeyer E.
;
Linhofer G.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
superconducting coils;
plasma simulation;
fusion reactor safety;
fusion reactor design;
fusion reactor operation;
plasma inertial confinement;
stellarators;
power supplies to apparatus;
eddy currents;
power supply circuits;
protection system simulation;
superconducting coil system;
Helias Stellarator Fusion Reactor;
stellarator fusion reactor configuration;
fusion power plant;
electric power;
safety system;
power supply unit;
coil group;
faults;
computer simulations;
SIMPLORER code;
induced eddy currents;
transient processes;
electric network analysis;
finite element network method;
18.
Structural response of the DIII-D toroidal field coil to increased lateral loads
机译:
DIII-D环形场线圈对横向载荷增加的结构响应
作者:
Reis E.E.
;
Chin E.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
electromagnets;
plasma toroidal confinement;
coils;
plasma transport processes;
finite element analysis;
physical instrumentation control;
structural response;
DIII-D toroidal field coil;
lateral load deflections;
calibration shots;
full toroidal field coil current;
maximum poloidal field coils;
coil bundle;
bending stiffness;
friction;
preloaded studs;
finite element structural model;
shear load distribution;
shear force;
magnetic fields;
plasma control system;
19.
Study of liquid metal film flow characteristics under fusion relevant magnetic field conditions
机译:
熔融相关磁场条件下液态金属膜流动特性的研究
作者:
Narula M.
;
Abdou M.A.
;
Ying A.Y.
;
Sketchley T.
;
Burris J.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
liquid films;
film flow;
fusion reactor divertors;
magnetohydrodynamics;
plasma toroidal confinement;
Tokamak devices;
plasma-wall interactions;
fusion reactor design;
liquid metal film flow;
fusion relevant magnetic field conditions;
particle pumping;
surface heat removal;
show-stoppers;
magnetohydrodynamic effects;
MHD;
free surface film flows;
NSTX;
film thickness streamwise variation;
film thickness spanwise variation;
film surface stability;
liquid surface divertor;
20.
Test of KSTAR ICRF components for long-pulse operation
机译:
KSTAR ICRF组件用于长脉冲操作的测试
作者:
Hong B.G.
;
Bae Y.D.
;
Hwang C.K.
;
Jung S.U.
;
Kwak J.G.
;
Wang S.J.
;
Yoon J.S.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
plasma radiofrequency heating;
Tokamak devices;
plasma toroidal confinement;
KSTAR ICRF components;
long-pulse operation;
high power ICRF components;
KSTAR tokamak;
high power density ICRF antenna;
water-cooled coaxial transmission;
electrical contact;
vacuum feedthrough;
RF power;
Al/sub 2/O/sub 3/;
ceramic cylinders;
O-ring seal;
phase shifter;
insulating dielectric medium;
RF tests;
peak voltage;
1 MW;
21.
The JET enhancement programme
机译:
JET增强计划
作者:
Damiani C.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
fusion reactor divertors;
plasma beam injection heating;
fusion reactor operation;
fusion reactor design;
antennas in plasma;
plasma diagnostics;
reviews;
JET enhancement programme;
JET operating domain;
ITER;
technological test-bed;
heating system;
plasma diagnostics;
control capabilities;
pellet fuelling system;
high triangularity;
divertor;
high power ITER-like plasmas;
neutral beam injector heating system;
JET Octant 8;
ITER-like ICRH antenna;
60-M/spl euro/-programme;
European Fusion Development Agreement;
EFDA;
tokamak physics;
burning plasma physics;
overview;
22.
Thermal study of the DIII-D machine heat removal capacity
机译:
DIII-D机散热能力的热学研究
作者:
Yip H.
;
Anderson P.M.
;
Holtrop K.L.
;
Harrison S.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
cooling;
fusion reactor materials;
fusion reactor operation;
fusion reactor design;
programmable controllers;
thermal analysis;
cooling towers;
thermal study;
DIII-D machine heat removal capacity;
plasma shot;
DIII-D tokamak;
energy dissipation;
cooling water system;
power supplies;
motor/generator;
rf current drives;
neutral beam power supplies;
magnetic field coils;
vacuum vessel;
isolated primary cooling loops;
isolated secondary cooling loops;
intermediate heat exchangers;
programmable logic controller;
heat generating sources;
heat transfer;
heat rejection;
cooling towers;
0.5 to 1.0 GJ;
23.
Turbulent velocity profile measurement in circular pipe flow using particle image velocimetry technique
机译:
用颗粒图像测速技术测量圆管内湍流速度分布。
作者:
Takeuchi J.
;
Miraghaie R.
;
Yuki K.
;
Satake S.
;
Kunugi T.
;
Morley N.B.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
boundary layer turbulence;
velocity measurement;
pipe flow;
velocimeters;
heat transfer;
fusion reactor blankets;
turbulent velocity profile measurement;
circular pipe flow;
particle image velocimetry;
turbulent flow;
thermofluid properties;
molten salt;
Flibe;
high Prandtl number fluid;
near wall flow structure;
turbulent statistics;
direct numerical simulation;
24.
Advanced tokamak plasmas in the fusion ignition research experiment
机译:
聚变点火研究实验中的先进托卡马克等离子体
作者:
Kessel C.E.
;
Meade D.
;
Swain D.W.
;
Titus P.
;
Ulrickson M.A.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
fusion reactor ignition;
plasma instability;
plasma magnetohydrodynamics;
plasma transport processes;
plasma simulation;
plasma radiofrequency heating;
advanced tokamak plasmas;
fusion ignition research experiment;
FIRE;
burning plasma experiment;
0D systems analysis;
equilibrium;
ideal MHD stability;
RF current drive analysis;
discharge dynamic simulations;
engineering constraints;
25.
Beam transport code for the KSTAR NB heating system
机译:
KSTAR NB加热系统的光束传输代码
作者:
Oh B.H.
;
Dlougach E.D.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
plasma beam injection heating;
particle beam dynamics;
Tokamak devices;
plasma toroidal confinement;
beam handling equipment;
beam handling techniques;
beam transport code;
KSTAR neutral beam heating system;
neutral beam production;
neutral beam transmission;
power deposition;
neutral beam line components;
operational conditions;
magnetic fields;
background gas;
beam losses;
residual magnetic field;
tokamak stray field;
reionized flux;
BTR code;
beam transport with reionization code;
26.
C-Mod cryo-pump design evaluation
机译:
C-Mod低温泵设计评估
作者:
Zaks J.
;
Vieira R.
;
Savelli H.
;
LaBombard B.
;
Irby J.
;
Titus P.
;
Childs R.
;
Zhukovsky A.
;
Lipshultz B.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
liquid helium;
Tokamak devices;
cryopumping;
fusion reactor design;
fusion reactor materials;
boiling;
heat transfer;
heat losses;
Alcator C-Mod tokamak;
cryo-pump pumping speed calculation;
helium tube sizing;
boiling heat transfer;
liquid helium;
cryopump protective shelf design;
cryopump protective shelf support;
heat loss;
cryogenic system design;
installation procedure;
He;
27.
Design of an induction heating system for the reassembly of the RFX machine
机译:
用于重新组装RFX机器的感应加热系统的设计
作者:
Masiello A.
;
Dal Bello S.
;
Fincato M.
;
Milani F.
;
Ravarotto D.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
copper;
shells (structures);
induction heating;
finite element analysis;
machine windings;
reversed field pinch;
fusion reactor materials;
fusion reactor design;
induction heating system;
RFX machine;
vacuum vessel;
copper shell;
electromagnetic finite element analysis;
thermal finite element analysis;
induction winding;
acquisition system;
Cu;
28.
Design of the PF system for EAST(HT-7U) tokamak
机译:
EAST(HT-7U)托卡马克PF系统的设计
作者:
Wu Weiyue
;
Li Baozeng
;
Zhuning
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
superconducting coils;
superconducting magnets;
niobium alloys;
titanium alloys;
PF system;
EAST(HT-7U) superconducting tokamak;
experimental advanced superconducting tokamak;
advanced steady-state plasma physics experimental device;
poloidal field coil system;
superconducting conductor;
NbTi cable-in-conduit conduct;
supercritical helium;
PF magnets;
superconducting coils;
equator plane;
engineering design;
magnetic field;
4.5 K;
29.
DIII-D plasma control simulation environment
机译:
DIII-D等离子控制仿真环境
作者:
Leuer J.A.
;
Deranian R.D.
;
Perron J.R.
;
Humphreys D.A.
;
Johnson R.D.
;
Penaflor E.G.
;
Walker M.L.
;
Welander A.S.
;
Khayrutdinov R.R.
;
Dokouka V.
;
Edgell D.H.
;
Fransson C.-M.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
physical instrumentation control;
plasma simulation;
plasma nonlinear waves;
tearing instability;
plasma magnetohydrodynamics;
DIII-D plasma control simulation environment;
hardware-in-the-loop plasma shape simulation capability;
nonlinear plasma evolution code;
DINA;
advanced neoclassical tearing mode;
resistive wall mode control;
30.
Efficiency improvement of AC/DC converter using SiC-based power electronics device
机译:
使用基于SiC的电力电子设备提高AC / DC转换器的效率
作者:
Matsukawa T.
;
Shimada R.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
power semiconductor devices;
fusion reactor design;
Tokamak devices;
AC-DC power convertors;
switching convertors;
power supplies to apparatus;
SiC-based power electronics device;
electrical characteristics;
SiC crystallized material;
switching element;
operational loss reduction;
resistance;
AC/DC converter system;
ITER class power supplies;
conventional thyristor AC/DC converter;
conduction loss;
31.
Electromechanical analysis of the JET MkII-HD divertor
机译:
JET MkII-HD偏滤器的机电分析
作者:
Riccardo V.
;
Villedieu E.
;
Altmann H.
;
Starkey D.
;
Baker R.
;
Eagle R.
;
Macmillan G.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
fusion reactor divertors;
fusion reactor design;
carbon fibre reinforced composites;
plates (structures);
electromechanical analysis;
JET MkII-HD divertor;
high triangularity plasmas;
load bearing septum replacement tiles;
high field side gap closure tiles;
divertor diagnostics;
metallic carriers;
carbon fiber composite base plates;
C;
32.
Engineering design of the quasi-poloidal stellarator (QPS)
机译:
准极化恒星(QPS)的工程设计
作者:
Nelson B.
;
Benson R.
;
Berry L.
;
Brooks A.
;
Cole M.
;
Fogarty P.
;
Fortier G.
;
Freudenberg K.
;
Goranson P.
;
Hargrove T.
;
Heitzenroeder P.
;
Hirshman S.
;
Jones G.
;
Lovett G.
;
Lyon J.
;
Madhukar M.
;
Mioduszewski P.
;
Monticello D.
;
Neilson G.
;
Parang M.
;
Spong D.
;
Strickler D.
;
Ware A.
;
Williamson D.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
design engineering;
stellarators;
machine components;
engineering design;
quasipoloidal stellarator experiment;
QPS;
manufacturing technique;
assembly technique;
stellarator core;
33.
Experimental study of gas flow through curved tubes in support of disruption mitigation experiments in DIII-D
机译:
支持DIII-D中减缓破坏实验的气流通过弯管的实验研究
作者:
Combs S.K.
;
Baylor L.R.
;
Foust C.R.
;
Jernigan T.C.
;
Tsai C.C.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
plasma beam injection heating;
plasma flow;
argon;
neon;
helium;
hydrogen;
gas flow;
curved tubes;
disruption mitigation experiments;
DIII-D tokamak;
high-pressure gas injection;
localized power deposition;
localized power forces;
internal components;
halo currents;
Ar;
Ne;
He;
H/sub 2/;
close-coupled stainless steel tubes;
relatively high gas load;
curved guide tubes;
magnetic high-field side pellet injection;
magnetic low-field side pellet injection;
exit ports;
inner wall;
tube diameters;
tube bore;
34.
Initial maintenance assessment for ARIES-CS power plant
机译:
ARIES-CS电厂的初步维护评估
作者:
Wang X.R.
;
Malang S.
;
Raffray A.R.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
stellarators;
fusion reactor design;
nuclear reactor maintenance;
initial maintenance assessment;
ARIES-CS power plant;
power core configurations;
modular scheme;
field-period scheme;
power core designs;
35.
Non-axisymmetric structural analyses of the new components for the modified RFX machine
机译:
改进的RFX机器新部件的非轴对称结构分析
作者:
Marcuzzi D.
;
Dal Bello S.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
reversed field pinch;
machine components;
plasma magnetohydrodynamics;
nonaxisymmetric structural analyses;
modified RFX machine;
mechanical analyses;
copper shell assembly;
toroidal support structure;
nominal condition;
fault condition;
joint zone;
critical zone;
MHD modes;
36.
Radiation environment for FIRE diagnostic ports
机译:
FIRE诊断端口的辐射环境
作者:
Sawan M.E.
;
Young K.M.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
neutron flux;
fusion reactor instrumentation;
plasma diagnostics;
nuclear radiation environment;
FIRE diagnostic ports;
Fusion Ignition Research Experiment;
two-dimensional neutronics calculations;
flux streaming;
port flange;
total neutron flux;
total gamma flux;
absorbed dose rates;
silica;
alumina;
4-bend penetrations;
radiation streaming calculations;
port plug;
cryostat interface;
fast neutron flux;
3.4 m;
1.1 m;
37.
Radiation resistance of fusion magnet materials
机译:
熔融磁铁材料的抗辐射性
作者:
Schultz J.H.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
neutron absorption;
fusion reactor ignition;
Tokamak devices;
plasma toroidal confinement;
high-temperature superconductors;
superconducting magnets;
organic insulating materials;
radiation resistance;
fusion magnet materials;
neutron absorption;
gamma ray absorption;
burning plasma experiments;
shield thickness;
fusion reactors;
insulation system;
superconducting copper magnet;
normal conducting copper magnet;
International Thermonuclear Experimental Reactor;
ITER;
unshielded insulation;
fusion ignition research experiment;
high radiation resistant organics;
potting properties;
wrappable ceramics;
ceramic-organic hybrids;
hardening superconducting materials;
nuclear radiation;
high-temperature superconductors;
BSSCO;
YBCO;
medium temperature superconductor;
MgB/sub 2/;
38.
Study on discharge characteristics of inertial electrostatic confinement fusion
机译:
惯性静电约束聚变的放电特性研究
作者:
Osawa H.
;
Kawame T.
;
Yoshioku S.
;
Ohnishi M.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
glow discharges;
electrostatic discharge;
fusion reactors;
plasma inertial confinement;
neutron sources;
Monte Carlo methods;
plasma simulation;
cathodes;
discharge characteristics;
inertial electrostatic confinement fusion device;
neutron source;
glow discharge;
two-dimensional Monte Carlo PIC code;
atomic processes;
discharge simulation;
D/sub 2//sup +/;
D/sub 2/ gas;
cathode;
39.
The restoration of the RFX power supply
机译:
恢复RFX电源
作者:
Piovan R.
;
De Lorenzi A.
;
Gaio E.
;
Milani F.
;
Toigo V.
;
Zanotto L.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
reversed field pinch;
power supplies to apparatus;
thyristors;
plasma magnetohydrodynamics;
DC-DC power convertors;
RFX power supply system restoration;
RFX machine;
plant safety;
RFP researches;
MHD mode control;
enhanced confinement regimes;
ignitrons;
power thyristors;
toroidal field power supply;
digital solutions;
converter control;
signal transmission;
power dc/dc converters;
40.
Thermal and mechanical analysis of PFC for SST-1 tokamak
机译:
SST-1托卡马克PFC的热力学分析
作者:
Chaudhuri P.
;
Santra P.
;
Ravi Prakash N.
;
Khirwadkar S.
;
Chenna Reddy D.
;
Saxena Y.C.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
thermal analysis;
Tokamak devices;
plasma toroidal confinement;
fusion reactor design;
fusion reactor divertors;
temperature distribution;
thermal stresses;
finite element analysis;
thermal analysis;
mechanical analysis;
PFC;
SST-1 tokamak;
plasma facing components;
Steady State Superconducting Tokamak;
steady state heat removal;
long pulse plasma operation;
high temperature plasma;
divertor;
passive stabilizers;
steady state tile temperature distribution;
transient tile temperature distribution;
thermally induced stresses;
thermally induced strains;
finite element method;
41.
Vacuum vessel contact dose build-up from start to end of ITER operations
机译:
从国际热核实验堆运行的开始到结束积累真空容器的接触剂量
作者:
Cambi G.
;
Cepraga D.G.
;
Frisoni M.
;
Carloni F.
;
Chiasera A.
会议名称:
《Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on》
|
2003年
关键词:
Tokamak devices;
plasma toroidal confinement;
fusion reactor operation;
fusion reactor materials;
fusion reactor design;
fusion reactor safety;
neutron effects;
vacuum vessel contact dose build-up;
ITER operations;
neutron fluence;
first wall;
ITER Generic Site Safety Report;
radial equatorial plane;
Sn calculation sequence SCALENEA-1;
FISPACT-99 activation code;
neutron irradiation;
remote handling operations;
maintenance cells;
20 s;
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