掌桥科研
一站式科研服务平台
科技查新
收录引用
专题文献检索
外文数据库(机构版)
更多产品
首页
成为会员
我要充值
退出
我的积分:
中文会员
开通
中文文献批量获取
外文会员
开通
外文文献批量获取
我的订单
会员中心
我的包量
我的余额
登录/注册
文献导航
中文期刊
>
中文会议
>
中文学位
>
中国专利
>
外文期刊
>
外文会议
>
外文学位
>
外国专利
>
外文OA文献
>
外文科技报告
>
中文图书
>
外文图书
>
工业技术
基础科学
医药卫生
农业科学
教科文艺
经济财政
社会科学
哲学政法
其他
工业技术
基础科学
医药卫生
农业科学
教科文艺
经济财政
社会科学
哲学政法
其他
自然科学总论
数学、物理、化学、力学
天文学、地球科学
生物科技
医学、药学、卫生
航空航天、军事
农林牧渔
机械、仪表工业
化工、能源
冶金矿业
电子学、通信
计算机、自动化
土木、建筑、水利
交通运输
轻工业技术
材料科学
电工技术
一般工业技术
环境科学、安全科学
图书馆学、情报学
社会科学
其他
马克思主义、列宁主义、毛泽东思想、邓小平理论
哲学、宗教
社会科学总论
政治、法律
军事
经济
文化、科学、教育、体育
语言、文字
文学
艺术
历史、地理
自然科学总论
数理科学和化学
天文学、地球科学
生物科学
医药、卫生
农业科学
工业技术
交通运输
航空、航天
环境科学、安全科学
综合性图书
自然科学总论
数学、物理、化学、力学
天文学、地球科学
生物科技
医学、药学、卫生
航空航天、军事
农林牧渔
机械、仪表工业
化工、能源
冶金矿业
电子学、通信
计算机、自动化
土木、建筑、水利
交通运输
轻工业技术
材料科学
电工技术
一般工业技术
环境科学、安全科学
图书馆学、情报学
社会科学
其他
自然科学总论
数学、物理、化学、力学
天文学、地球科学
生物科技
医学、药学、卫生
航空航天、军事
农林牧渔
机械、仪表工业
化工、能源
冶金矿业
电子学、通信
计算机、自动化
土木、建筑、水利
交通运输
轻工业技术
电工技术
一般工业技术
环境科学、安全科学
图书馆学、情报学
社会科学
其他
自然科学总论
数学、物理、化学、力学
天文学、地球科学
生物科技
医学、药学、卫生
航空航天、军事
农林牧渔
机械、仪表工业
化工、能源
冶金矿业
电子学、通信
计算机、自动化
土木、建筑、水利
交通运输
轻工业技术
材料科学
电工技术
一般工业技术
环境科学、安全科学
图书馆学、情报学
社会科学
其他
美国国防部AD报告
美国能源部DE报告
美国航空航天局NASA报告
美国商务部PB报告
外军国防科技报告
美国国防部
美国参联会主席指示
美国海军
美国空军
美国陆军
美国海军陆战队
美国国防技术信息中心(DTIC)
美军标
美国航空航天局(NASA)
战略与国际研究中心
美国国土安全数字图书馆
美国科学研究出版社
兰德公司
美国政府问责局
香港科技大学图书馆
美国海军研究生院图书馆
OALIB数据库
在线学术档案数据库
数字空间系统
剑桥大学机构知识库
欧洲核子研究中心机构库
美国密西根大学论文库
美国政府出版局(GPO)
加利福尼亚大学数字图书馆
美国国家学术出版社
美国国防大学出版社
美国能源部文献库
美国国防高级研究计划局
美国陆军协会
美国陆军研究实验室
英国空军
美国国家科学基金会
美国战略与国际研究中心-导弹威胁网
美国科学与国际安全研究所
法国国际关系战略研究院
法国国际关系研究所
国际宇航联合会
美国防务日报
国会研究处
美国海运司令部
北约
盟军快速反应部队
北约浅水行动卓越中心
北约盟军地面部队司令部
北约通信信息局
北约稳定政策卓越中心
美国国会研究服务处
美国国防预算办公室
美国陆军技术手册
一般OA
科技期刊论文
科技会议论文
图书
科技报告
科技专著
标准
其它
美国卫生研究院文献
分子生物学
神经科学
药学
外科
临床神经病学
肿瘤学
细胞生物学
遗传学
公共卫生&环境&职业病
应用微生物学
全科医学
免疫学
动物学
精神病学
兽医学
心血管
放射&核医学&医学影像学
儿科
医学进展
微生物学
护理学
生物学
牙科&口腔外科
毒理学
生理学
医院管理
妇产科学
病理学
生化技术
胃肠&肝脏病学
运动科学
心理学
营养学
血液学
泌尿科学&肾病学
生物医学工程
感染病
生物物理学
矫形
外周血管病
药物化学
皮肤病学
康复学
眼科学
行为科学
呼吸学
进化生物学
老年医学
耳鼻喉科学
发育生物学
寄生虫学
病毒学
医学实验室检查技术
生殖生物学
风湿病学
麻醉学
危重病护理
生物材料
移植
医学情报
其他学科
人类生活必需品
作业;运输
化学;冶金
纺织;造纸
固定建筑物
机械工程;照明;加热;武器;爆破
物理
电学
人类生活必需品
作业;运输
化学;冶金
纺织;造纸
固定建筑物
机械工程;照明;加热;武器;爆破
物理
电学
马克思主义、列宁主义、毛泽东思想、邓小平理论
哲学、宗教
社会科学总论
政治、法律
军事
经济
文化、科学、教育、体育
语言、文字
文学
艺术
历史、地理
自然科学总论
数理科学和化学
天文学、地球科学
生物科学
医药、卫生
农业科学
工业技术
交通运输
航空、航天
环境科学、安全科学
综合性图书
主题
主题
题名
作者
关键词
摘要
高级搜索 >
外文期刊
外文会议
外文学位
外国专利
外文图书
外文OA文献
中文期刊
中文会议
中文学位
中国专利
中文图书
外文科技报告
清除
历史搜索
清空历史
首页
>
外文会议
>
其他
>
IEEE/NPSS Symposium on Fusion Engineering
IEEE/NPSS Symposium on Fusion Engineering
召开年:
召开地:
出版时间:
-
会议文集:
-
会议论文
热门论文
全部论文
全选(
0
)
清除
导出
共
697
条结果
1.
Advanced antenna for ICRF Plasma Heating and high frequency fast wave Current Drive in large fusion machines and ITER
机译:
用于ICRF等离子加热和大型融合机和磨练的高频快速波电流驱动的先进天线
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antenna travelling wave arrays;
high-frequency effects;
plasma density;
plasma heating;
plasma toroidal confinement;
stellarators;
3D ICRF;
3D RF full wave codes modeling;
3D in-port antennae ANPORT codes;
ANTRES3 codes;
DIII-D;
ECRF;
HFFW;
ITER;
NBI;
TWA;
antenna-plasma coupling;
current drive plasma-wave interaction;
high frequency fast wave current drive;
large fusion machines;
mirror traps;
plasma edge density;
tokamaks;
toroidally broad multiloop traveling wave antenna;
2.
Numerical analysis of using a fluidized bed as a prototypic mass production device for IFE target layering
机译:
流化床作为IFE靶分层原型批量生产装置的数值分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
cryogenics;
fusion reactor design;
fusion reactor targets;
fusion reactor theory;
numerical analysis;
plasma inertial confinement;
IFE target layering;
controlled gas stream;
cryogenic condition;
fluidized bed model;
ice layer;
inertial fusion energy target design;
near-isothermal environment;
prototypic mass production device;
Fluidized bed;
IFE-target layering;
3.
Performance study of non-contact surface measurement technology for use in an experimental fusion device
机译:
实验融合装置中使用非接触表面测量技术的性能研究
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor materials;
measurement;
plasma-wall interactions;
EFDA-JET;
first wall protection tiles;
fusion device;
metrology techniques;
noncontact surface scanning;
plasma facing components;
remote handling;
shutdown periods;
laser scanner;
metrology;
surface measurement;
4.
A fast exhaust-gas analyzer for the ITER divertor
机译:
用于磨损器的快速排气分析仪
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
electrodes;
fusion reactor divertors;
fusion reactor operation;
magnetic fields;
plasma diagnostics;
sensors;
ITER divertor;
electrodeless operation;
magnetic field;
metal rf electrodes;
neutralization region;
plasma excitation;
plasma light emission;
radiation-enhanced breakdowns;
rf-excited optical gas analyzer;
sensor head;
ITER;
divertor;
helium exhaust;
helium removal;
residual gas analysis;
5.
Low distortion welded joints for NCSX*
机译:
用于NCSX的低失真焊接接头*
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
coils;
fusion reactor design;
fusion reactor instrumentation;
fusion reactor materials;
fusion reactor operation;
nuclear engineering;
plasma toroidal confinement;
stainless steel;
stellarators;
Miller Axcess equipment;
NCSX;
austenitic 316 stainless steel;
half field-period assemblies;
low distortion welded joints;
magnetic fields;
modular coil windings;
modular field coils;
stainless steel alloy;
welded shear plate;
National Compact Stellarator Experiment;
shear plate design;
welding;
welding processes;
6.
NSTX protection and interlock systems for coil and powers supply systems
机译:
线圈和电源供应系统的NSTX保护和互锁系统
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor safety;
nuclear engineering computing;
physical instrumentation control;
power supplies to apparatus;
NSTX protection systems;
PF magnetic coils;
Princeton Plasma Physics Laboratory;
TF magnetic coils;
electromagnetic fields;
electromechanical forces;
interlock systems;
plasma control;
plasma positioning control system;
powers supply systems;
stable plasma operation;
Coil;
Detection;
Fault;
Overcurrent;
Permissive;
Power;
Protection;
Rectifier;
7.
Calculated beam profiles for the DIII-D off-axis and long pulse neutral beam upgrade
机译:
计算DIII-D离轴和长脉冲中性光束升级的光束配置
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
fusion reactor materials;
plasma beam injection heating;
Cartesian coordinates;
DIII-D off-axis;
Gaussian point sources;
beamline internal components;
long pulse neutral beam;
neutral beam injection;
neutral beam ion sources;
scrape-off beam power loss;
water-flow-calorimetry;
8.
Parametric analysis of the helium flow for the in-bed calorimetry of metal hydride bed
机译:
金属氢化物床上床上热量氦流量的参数分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
calorimetry;
cobalt alloys;
fusion reactor materials;
fusion reactor theory;
helium;
numerical analysis;
radioactive waste disposal;
thin films;
zirconium alloys;
ITER storage-delivery system;
ZrCoJk;
cylinder-shaped SUS filter;
helium channels;
helium flow;
in-bed calorimetry;
parametric analysis;
primary vessel wall;
thin double-layered annulus metal hydride bed;
three-dimensional numerical simulation;
tritium;
CFD;
ITER;
Metal hydride bed;
SDS;
component;
9.
Simulation experiment of thermal transient events in ITER by use of magneti zed coaxial plasma gun
机译:
磁铁同轴等离子体枪仿真探测热瞬态事件的实验
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
arcs (electric);
calorimeters;
electron density;
fusion reactor divertors;
plasma density;
plasma guns;
plasma simulation;
Hlt;
subgt;
2lt;
/subgt;
plasma;
ITER;
MCPG;
calorimeter;
fusion reactor divertor;
magnetized coaxial plasma gun;
plasma discharge;
plasma irradiation;
thermal transient events;
type I ELM;
divertor;
transient heat load;
tungsten;
10.
Performance analysis for an infrared second harmonics dispersion interferometer
机译:
红外二级谐波色散干涉仪的性能分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
light interferometers;
optical harmonic generation;
optical phase matching;
TEXTOR tokamak;
dispersion interferometer;
fusion devices;
highly compact frameless design;
infrared second harmonic generation;
infrared spectrum;
line-integrated density;
multichannel diagnostics;
nonlinear optical crystal;
phase-matching angle;
second probing beam;
two-color interferometer;
Interferometry;
performance analysis;
second harmonics interferometer;
11.
Operational activity evaluation of ITER diagnostic neutron activation system
机译:
迭代诊断中子激活系统的操作活动评估
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
aluminium;
copper;
fusion reactor materials;
gamma-ray effects;
iron;
neutron effects;
niobium;
plasma diagnostics;
plasma-wall interactions;
silicon;
titanium;
Al;
Cu;
Fe;
ITER diagnostic neutron activation system;
Nb;
Si;
Ti;
fusion power;
gamma radiation;
midplane inboard region;
neutron flux;
neutron irradiation;
neutronics calculations;
operational activity evaluation;
FISPACT Alite;
ITER;
MCNP;
neutron activation system;
sample activity;
12.
Models and experiments for liquid metal-water interaction in fusion reactor blankets
机译:
融合反应堆毛毡液态金属 - 水相互作用的模型及实验
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor blankets;
fusion reactor safety;
liquid metals;
water;
fission reactors;
heavy liquid metals;
liquid metal-water interaction;
pressurized water;
experiments of interaction with water;
simplified model of water injection in a liquid metal pool;
13.
KSTAR Charge Exchange Spectroscopy system
机译:
KSTAR电荷交换光谱系统
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
charge-coupled devices;
fusion reactor design;
plasma beam injection heating;
plasma diagnostics;
plasma flow;
CCD detector;
Czerny-Turner spectrometer;
KSTAR CES diagnostics;
KSTAR charge exchange spectroscopy system;
Korea superconducting tokamak advanced research;
cassette system;
helium discharge;
impurity density;
international tokamaks;
lens design;
modulated neutral beam injection;
poloidal rotation;
quartz fibers;
thinned back-illuminated charge coupled device;
toroidal rotation;
14.
Closed-loop identification and controller reconfiguration for EXTRAP T2R reversed-field pinch
机译:
闭环识别和控制器重新配置用于升空T2R反向场夹紧
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
closed loop systems;
feedback;
fusion reactor instrumentation;
fusion reactor operation;
nuclear engineering;
physical instrumentation control;
reversed field pinch;
EXTRAP T2R reversed-field pinch;
closed-loop identification;
controller reconfiguration;
multi-input-multi-output controller;
reconfigured feedback system;
15.
Utilizing zfs for the storage of acquired data
机译:
利用ZFS来存储所获取的数据
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
data acquisition;
disc storage;
high energy physics instrumentation computing;
UNIX filesystem partitions;
ZFS;
acquired data storage;
administrators;
data storage;
disk file system;
hard drive storage space;
plasma experiments;
UNIX;
storage;
16.
Simulation results for new NSTX HHFW antenna straps design by using microwave studio
机译:
使用微波工作室的新NSTX HHFW天线带设计的仿真结果
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antennas;
antennas in plasma;
fusion reactor design;
fusion reactor ignition;
microwave antennas;
plasma heating;
plasma simulation;
NSTX antenna straps design;
NSTX spherical tokamak operation;
associated resonant loops;
high harmonic fast wave;
microwave studio;
plasma current drive heating;
substantial plasma heating;
17.
Progress in design integration and configuration control of the ITER machine baseline
机译:
ITER机器基线设计集成和配置控制的进展
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor operation;
ITER configuration management models;
ITER machine baseline design integration;
ITER operation;
commissioning;
configuration control;
ITER;
baseline;
configuration;
integration;
tokamak;
18.
Beryllides for fusion reactors
机译:
融合反应堆的铍
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
radiation effects;
thermal conductivity;
tritium handling;
ITER;
beryllides;
beryllium intermetallic compound;
ceramic breeder blankets;
erosion;
first wall;
fusion reactors;
irradiation effects;
light-weight materials;
plasma facing component;
reactivity;
tritium release;
PFC;
beryllide;
beryllium;
blanket;
nuclear fusion reactor;
pebble beds;
19.
Testing of compact bolted fasteners with insulation and friction-enhanced shims for NCSX
机译:
用绝缘和摩擦增强垫片的紧凑型螺栓固定螺栓用于NCSX的测试
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
coils;
fusion reactor design;
fusion reactor materials;
plasma toroidal confinement;
stellarators;
G-10 insulators;
NCSX;
National Compact Stellarator Experiment;
bushings;
compact bolted fasteners;
electrical tests;
friction;
insulating spacers;
jack nuts;
liquid nitrogen temperatures;
modular coils;
stellarator designs;
tension relaxation tests;
toroidal field coils;
Bolting;
Cryogenic;
Stellerator;
Testing;
20.
Critical issues for disposal, recycling, and clearance of fusion radioactive materials: The European viewpoint
机译:
处理,回收和融合放射性物质的关键问题:欧洲观点
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor materials;
nuclear facility decommissioning;
nuclear power stations;
radioactive waste disposal;
radioactive waste processing;
European fusion study;
components;
decommissioning;
fission power plants;
fusion power generation;
fusion radioactive materials;
low-level waste disposal;
material recycling;
waste management scheme;
European Union;
activation;
clearance;
fusion back-end;
radioactive waste;
recycling;
21.
Baseline system design and prototyping for the ITER high-frequency magnetic diagnostics set
机译:
基线系统设计与原型为艾特高频磁诊断集
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor materials;
high-frequency effects;
plasma diagnostics;
ITER high-frequency magnetic diagnostics set;
W;
baseline system design;
intrinsic spatial periodicity;
low temperature Co-fired ceramic technology;
unguided tungsten wire;
ITER;
LTCC;
high-frequency magnetic diagnostic;
22.
Construction of Wendelstein 7-X - Engineering a steady state stellarator
机译:
WENDELSTEIN 7-X - Engineering稳态螺栓施工
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor divertors;
fusion reactor operation;
plasma magnetohydrodynamics;
stellarators;
superconducting coils;
MHD stability;
divertor chamber;
economic fusion reactor;
reactor plasma condition;
steady state stellarator operation;
superconducting device Wendelstein 7-X;
Wendelstein 7-X;
component;
construction;
optimized stellarator;
steady-state operation;
23.
Analysis of DIII-D upgraded neutral beamline bending magnet thermal shields
机译:
DIII-D升级中性光束线弯曲磁铁分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
24.
Manufacturing of BERYLLIUM TILES for the JET ITER-like wall project
机译:
用于喷气式机样墙壁项目的铍瓷砖制造
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
beryllium;
fusion reactor design;
fusion reactor materials;
internal stresses;
plasma-wall interactions;
Be;
Commission of European Community;
European Atomic Energy Community;
JET ITER-like wall project;
beryllium wall tile design;
contamination control;
inconel carriers;
residual stress;
ITER-Like Wall Project;
Joint European Torus (JET);
plasmafacing components (PFCs);
25.
Elements of successful and safe fusion experiment operations
机译:
成功和安全融合实验操作的元素
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor operation;
fusion reactor safety;
nuclear facility regulation;
nuclear reactor maintenance;
JWG;
Japanese fusion experiments;
Joint Working Group;
US Safety Monitor team;
fusion facility;
fusion safety operations;
maintenance;
26.
Diagnostic neutral beam for ITER - Concept to engineering
机译:
诊断中性光束iter - 工程概念
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
cryopumping;
fusion reactor design;
fusion reactor ignition;
fusion reactor instrumentation;
fusion reactor materials;
nuclear engineering;
plasma beam injection heating;
CODAC;
ITER;
Ion Source Test Facility;
beam line components;
comprehensive prototyping phase;
cryo pumping;
diagnostic neutral beam;
electrical design;
hydraulic pumping;
optimal beam line configuration;
pneumatic pumping;
transmission;
vacuum pumping;
vessel components;
beam transmission;
beamline components;
concept;
27.
Preliminary thermo-hydraulic analysis of the Breeder Zone for the EU helium cooled pebble bed test blanket module for ITER
机译:
欧盟氦气冷却鹅卵石床试验毯模块饲养区的初步热水水力分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
fusion reactor design;
EU helium cooled pebble bed test blanket module;
ITER;
TBM structural component;
breeder zone;
heat flux;
reactor design;
thermo-hydraulic analysis;
BZ;
Heilum Cooled Pebble Bed Test Blanket Modul (HCPB TBM)e;
Pebble beds;
Solid Breeder Concept;
28.
Disruption mitigation technology concepts and implications for ITER
机译:
中断缓解技术概念和对ITER的影响
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
plasma magnetohydrodynamics;
ITER;
MHD instabilities;
deuterium gas;
disruption mitigation technology;
electron conversion;
halo currents;
heat flux;
helium gas;
plasma energy;
tokamak exhaust processing system;
vacuum system;
disruption;
pellet;
29.
Diffusion and solution of hydrogen isotopes in lithium-lead blanket materials
机译:
锂引线橡皮布材料中氢同位素的扩散与溶液
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
desorption;
diffusion;
dissolving;
fusion reactor blankets;
fusion reactor safety;
lead alloys;
liquid alloys;
lithium alloys;
powders;
silicon compounds;
sintering;
solubility;
wide band gap semiconductors;
Lilt;
subgt;
17lt;
/subgt;
Pblt;
subgt;
83lt;
/subgt;
SiC;
activation energy;
deuterium;
dissolution;
hydrogen isotopes;
liquid alloy;
lithium-lead blanket materials;
powder;
sintering additive;
Silicon carbide;
component;
lithium-lead;
solution;
tritium diffusion;
30.
Application of high-performance aerogel insulating materials (analysis #x00026; test results)
机译:
高性能气凝胶绝缘材料的应用(分析与测试结果)
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
31.
Mission and overview of a Fusion Development Facility
机译:
融合开发机构的使命及概述
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
hydrogen production;
research and development;
tritium handling;
ARIES-AT device;
DEMO;
IFMIF;
ITER;
T;
advanced Tokamak physics;
blankets;
fusion demonstration power plant;
fusion development facility;
fusion fuel cycle;
fusion nuclear component;
neutron flux;
nonsuperconducting magnet technology;
tritium;
component;
formatting;
style;
styling;
32.
Real-time reconstruction of the magnetic flux in ftu using multipolar current moments
机译:
使用多极电流时刻的FTU中磁通量的实时重建
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
magnetic fields;
magnetic flux;
plasma boundary layers;
FTU;
Grad-Shafranov equation;
magnetic field;
magnetic iso-flux surface;
magnetic surfaces;
multipolar current moments;
multipolar moment method;
plasma boundary condition;
plasma control;
real-time reconstruction;
tokamak machines;
33.
Progress on the ITER electron cyclotron heating and current drive upper launcher steering mirror control system
机译:
ITER电子回旋加热和电流驱动器上发射器转向镜控制系统的进展
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
magnetohydrodynamics;
plasma oscillations;
plasma radiofrequency heating;
plasma switches;
steering systems;
ITER electron cyclotron heating;
Neoclassical Tearing Modes;
current drive upper launcher steering mirror control system;
magnetohydrodynamic activity;
modulation rotation cycles;
permanent tracking error;
steering mechanism assembly;
switching cycles;
34.
High heat flux test with HIP bonded Be/Cu mock-ups for the ITER first wall
机译:
具有髋关节的高热通量试验为磨损的磨损器第一墙/ Cu模拟
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fatigue;
fusion reactor blankets;
hot pressing;
nuclear engineering computing;
ANSYS;
Be-CuCrZr-FeCrCJk;
HIP bonded mock-ups;
ITER blanket first wall;
International Thermonuclear Experimental Reactor;
KAERI;
KoHLT-1;
fatigue lifetime;
graphite heater facility;
heat sink material;
high heat flux test;
hot isostatic pressing;
Be/Cu/SS mock-up;
First Wall;
HHF test;
HIP;
ITER;
Qualification test;
35.
Continuum-transition models of neutralizer gas heating
机译:
中载器气体加热连续过渡模型
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
fusion reactor targets;
fusion reactor theory;
plasma beam injection heating;
Augmented Burnett Equations;
ITER;
JET positive neutral injection;
consistent gas-beam-plasma system;
continuum-transition gas flow;
continuum-transition models;
gas sources;
neutral beam injection system;
neutralization target;
neutralizer gas heating;
positive ion neutral beam systems;
continuum-transition;
gas heating;
neutralizer;
36.
Detailed heat loads into ITER castellated divertor gaps uring ELMs
机译:
详细的热量负荷进入浸泡埃尔姆斯的艾滋病
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor divertors;
plasma deposition;
plasma impurities;
plasma sheaths;
plasma simulation;
plasma toroidal confinement;
tritium handling;
ELM;
ITER;
castellated divertor gaps;
heat flux;
kinetic calculations;
magnetic field;
plasma facing components;
plasma impurity;
plasma sheath;
radioactivity;
tritium deposition;
gaps;
kinetic modeling;
sheath;
37.
Sputtering studies of lithiated ATJ graphite by lithium ion bombardment
机译:
锂离子轰击锂化ATJ石墨的溅射研究
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
graphite;
ion-surface impact;
microbalances;
powders;
sputtering;
ATJ graphite;
C;
Colutron ion source;
LiCl;
deuterium saturation treatment;
divertor;
electron volt energy 700 eV to 2000 eV;
lithium ion bombardment;
nonsaturated samples;
quartz crystal microbalance;
component;
lithium;
38.
Massive pellet and rupture disk testing for disruption mitigation applications
机译:
中断缓解应用的巨大颗粒和破裂盘试验
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
cryogenics;
fusion reactor divertors;
fusion reactor targets;
plasma boundary layers;
refrigerators;
DIII-D;
cryogenic refrigerator;
divertor;
double-impact target;
massive pellet;
noble gases;
plasma boundary;
rupture disk testing;
tokamaks;
disruption;
gas injection;
mitigation;
plasma;
rupture disk;
39.
Experimental analysis of MHD pressure drop in a HCLL blanket mock-up
机译:
HCLL毯子模拟中MHD压降的实验分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
fusion reactor operation;
lead alloys;
lithium alloys;
plasma magnetohydrodynamics;
HCLL blanket mock-up;
ITER;
MHD pressure drop;
PbLi;
flow rate;
helium cooled lead lithium blanket;
magnetic field intensity;
magneto-hydrodynamic liquid metal;
operational capability;
pressure distribution;
40.
Plasma and current drive parameter options for a megawatt range fusion neutron source
机译:
兆瓦范围融合中子源的等离子体和电流驱动参数选项
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
fusion reactor operation;
neutron sources;
plasma heating;
plasma simulation;
DEMO;
auxiliary heating;
current drive parameter;
fast nuclear reactors;
fusion power;
megawatt range fusion neutron source;
nuclear fuel cycle;
steady-state plasma discharges;
subcritical active zones;
tokamak size;
fusion neutron source;
steady state operation;
tokamak;
41.
Design of the Breeder Zone for the EU Helium Cooled Pebble Bed Test Blanket Module for ITER
机译:
EU氦气冷却卵石床试验毯模块的饲养区设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
fusion reactor design;
milling;
welding;
EU helium cooled pebble bed test blanket module breeder zone;
ITER;
milling-diffusion welding;
spark erosion;
thermohydraulic behavior;
Blanket mannufacturing;
Breeder Blanket;
Breeder Zone (BZ);
HCPB TBM;
Solid breeder concept;
42.
Analysis of DIII-D neutral beam power systems for 10 second operation
机译:
DIII-D中性光束电力系统10秒运行分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
ion sources;
plasma beam injection heating;
power supplies to apparatus;
DIII-D neutral beam power systems;
DIII-D tokamak;
beam line components;
downstream grid control supplies;
high power beam voltage supply;
ion source arc;
neutral beam injector systems;
neutral beam power systems;
noninductive neutral beam current drive;
DIII-D;
Neutral Beams;
Power supplies;
long pulse;
43.
Recent advances in ST research and prospects for new ST capabilities
机译:
新的ST研究和前景的最新进展
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antennas in plasma;
fusion reactor design;
fusion reactor divertors;
plasma diagnostics;
DEMO design optimisation;
HHFW antenna;
ST research;
fusion component test facility;
high resolution diagnostics;
liquid lithium divertor;
spherical tokamak research;
MAST;
NSTX;
QUEST;
component test facility;
spherical tokamak;
44.
New alcator C-Mod rotated 10#x00B0; 4-strap ICRF antenna
机译:
新的Alcator C-Mod旋转10°4-STRAP ICRF天线
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antennas in plasma;
fusion reactor design;
nuclear engineering computing;
plasma radiofrequency heating;
Alcator C-Mod;
CST computer code;
ICRF impurity production;
Tore Supra;
magnetic field;
rotated 4-strap ICRF antenna;
45.
Measurement of disruption forces in JET using fiber-optic sensors
机译:
使用光纤传感器测量喷射中的破坏力
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Bragg gratings;
Tokamak devices;
fibre optic sensors;
fusion reactor divertors;
strain gauges;
transducers;
JET;
VDE;
broadband light source;
divertor coils;
fiber bragg gratings;
fiber-optic sensors;
optical fiber transducers;
vacuum vessel;
vertical displacement event;
46.
ITER central solenoid alternate pre-compression structure - Concept and analysis
机译:
ITER中央电磁阀交替预压缩结构 - 概念和分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
eddy currents;
fusion reactor design;
plasma heating;
plasma toroidal confinement;
solenoids;
ITER central solenoid;
US ITER Project Office;
current pulse;
end of burn;
pre-compression support structure;
preliminary eddy current heat;
tension rod;
toroidal field coil bore;
transient electromagnetic FEA;
Central Solenoid;
Eddy Current Heating;
FEA;
ITER;
Stress Analysis;
component;
47.
Benchmarking FENDL-2.1 with impact of ENDF/B-VII.0 release on nuclear heating and damage
机译:
基准测试Fendl-2.1具有Endf / B-VII.0释放对核加热和损伤的影响
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor targets;
fusion reactor theory;
radiation effects;
ENDF-B-VII.0 data;
FENDL-2.1library;
ICF target;
ITER calculational benchmark;
ITER design;
MCNP calculations;
energy spectrum;
fusion evaluated nuclear data library;
inertial fusion power plant;
nuclear heating;
nuclear parameters;
radiation damage;
ITER;
nuclear data;
48.
Updated design of the ITER magnet system gravity supports
机译:
更新的ITER磁铁系统重力支持设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor safety;
superconducting magnets;
ITER superconducting magnet design;
defects;
gravity supports;
manufacturing cost;
prestressed bolted connections;
welded connections;
ITER;
magnets;
tokamak;
49.
Transient thermal and stress response of a helium-cooled tungsten plate-type divertor
机译:
氦气冷却钨板型隅锥体的瞬态热和应力响应
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor divertors;
fusion reactor operation;
thermal stresses;
thermomechanical treatment;
tungsten alloys;
ARIES;
MFE fusion power plant application;
WJkJk;
helium-cooled tungsten-alloy plate-type divertor configuration design;
plant shutdown operation;
power plant assembly units;
thermo-fluid analysis;
thermomechanical analysis;
transient thermal stress analysis;
divertor;
fusion power plant;
thermal-fluid response;
thermo-mechanical response;
50.
Effects of the grid breakdowns on the acceleration Grid Power supply of the ITER NBI
机译:
电网故障对磨机NBI加速电网电力供应的影响
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
plasma beam injection heating;
power supplies to apparatus;
AGPS;
ITER;
NBI;
acceleration grid power supply;
current stresses;
grid breakdown effects;
high-frequency model;
neutral beam injector;
power supply terminals;
voltage oscillations;
voltage stresses;
breakdown;
power supply;
51.
The magnetic diagnostic set for ITER
机译:
磁性诊断设置为erter
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor instrumentation;
fusion reactor safety;
plasma diagnostics;
ITER;
Ramp;
amp;
D activity;
magnetic diagnostic set;
magneto-hydrodynamic modes;
physics diagnostics functions;
magnetic diagnostic system;
52.
Generation of neutron beam by the cylindrical discharge fusion device
机译:
通过圆柱形放电熔融装置产生中子束
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Monte Carlo methods;
fusion reactor design;
neutron reflection;
neutron sources;
neutron transport theory;
nuclear engineering computing;
nuclear fusion;
Dlt;
subgt;
2lt;
/subgt;
O reflector;
Hlt;
subgt;
2lt;
/subgt;
O reflector;
MCNP;
cylindrical discharge fusion device;
discharge-type tube shaped neutron source;
electrodes;
fusion reactions;
neutron beam generation;
neutronic analyses;
reflector design;
three-dimensional particle transport code;
cylindrical discharge fusion;
neutron beam;
neutron generator;
53.
ELM suppression by resonant magnetic perturbations at DIII-D
机译:
ELM抑制在DIII-D的共振磁扰动
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor materials;
plasma boundary layers;
plasma collision processes;
plasma flow;
plasma instability;
DIII-D;
ELM;
ITER;
distant coil arrays;
edge collisionalities;
edge localized mode suppression;
plasma rotation;
plasma shapes;
poloidally-tall arrays;
resonant magnetic perturbations;
spatial helical harmonic spectra;
RMP;
edge localized mode;
magnetic perturbations;
54.
Heat transfer of free surface MHD-flow with a wall of non-uniform electrical conductivity
机译:
自由表面MHD流动的热传递与非均匀导电率的壁
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Luders bands;
boundary layers;
electrical conductivity;
heat transfer;
magnetohydrodynamics;
Hartmann numbers;
Lorentz forces;
boundary layer thickness;
free surface magnetohydrodyanmics-flow;
friction factors;
nonuniform electrical conductivity;
Free Surface;
Heat Transfer Enhancement;
Magnetohydrodynamic;
Non-uniform Electrical Conductivity;
55.
Model of environmental tritium behavior and effect of aquatic system in Japan.
机译:
日本水产系统的环境氚行为模型及其影响。
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
agricultural pollution;
dosimetry;
fusion reactor operation;
fusion reactor theory;
tritium handling;
water pollution;
NORMTRI code;
agricultural product;
aquatic system;
coastal area;
environmental condition;
environmental tritium behavior;
food contamination;
fusion plant operation;
tritium dose assessment;
water contamination;
NORMTRI;
environment;
tritium;
56.
Jet operations and plasma control: A plasma control system that is safe and flexible in a manageable way.
机译:
喷射操作和等离子控制:等离子控制系统,可以可管理的方式安全灵活。
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor operation;
physical instrumentation control;
plasma density;
ITER;
Tokamak system;
plasma control system;
plasma operation;
JET;
Plasma Control;
Real Time;
57.
ITER ICRF system: R#x00026;D progress and technical choices
机译:
ITER ICRF系统:研发进展和技术选择
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antennas in plasma;
plasma radiofrequency heating;
research and development;
ITER ICRF system;
Ramp;
amp;
D progress;
antenna;
ITER;
Matching;
Power supplies;
Procurement;
Radio-Frequency;
transmission line;
58.
Stack monitor operating experience review
机译:
堆栈监控操作体验评论
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
air pollution;
fusion reactor instrumentation;
fusion reactor operation;
nuclear facility regulation;
radiation monitoring;
DOE;
National Ignition Facility;
ORPS;
Occurrence Reporting and Processing System;
U.S. Department of Energy;
air protection;
electrical faults;
gases;
international ITER project;
nuclear facility;
radiation instrumentation faults;
radioactive particulates;
stack monitor operation;
maintainability;
reliability;
stack monitoring;
59.
Upgrade of the ICRF fault and control systems on alcator C-Mod
机译:
Alcator C-Mod上的ICRF故障和控制系统升级
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
antennas in plasma;
fusion reactor instrumentation;
fusion reactor materials;
physical instrumentation control;
plasma radiofrequency heating;
power transmission faults;
power transmission reliability;
transmission lines;
Alcator C-Mod;
C-Mod tokamak;
RF power;
RF regulation system;
antenna protection system;
control systems;
fault processing components;
feedback elements;
four-strap antenna;
ion cyclotron RF transmitter system;
master fault processor;
plasma loads;
power 2 MW;
switching components;
60.
Copper alloys used for support units of ITER blanket modules: Compression and tension properties
机译:
用于浸泡装置的铜合金毯子模块:压缩和张力性能
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
ageing;
chromium alloys;
compressive strength;
copper alloys;
fusion reactor blankets;
fusion reactor design;
solution annealing;
tensile strength;
thermal expansion;
yield stress;
zirconium alloys;
CuCrZr;
ITER blanket modules;
ITER design;
SDC-IG;
aging;
compression;
first wall module;
flexible cartridge;
in-vessel components;
structural analysis;
structural design criteria;
tensile data;
tension property;
vacuum vessel;
ITER components;
compression properties;
tensile properties;
61.
Copyright page
机译:
版权页面
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
62.
Completing the viability demonstration of direct-drive inertial fusion energy target engagement
机译:
完成直接驱动惯性融合能源目标参与的可行性演示
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor design;
fusion reactor reaction chamber;
fusion reactor targets;
laser fusion;
High Average Power Laser program;
axial target detection technique;
direct-drive inertial fusion energy target engagement;
engagement system;
final correction technique;
implosion;
inertial fusion power plant;
multiple laser beam alignment;
short-pulse laser;
steering mirrors;
target tracking;
transverse target detection technique;
vacuum environment;
Poisson spot;
component;
glint system;
target tracking and engagement;
63.
Neutronic analysis of FAST
机译:
快速的中性分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Monte Carlo methods;
Tokamak devices;
fusion reactor design;
fusion reactor divertors;
fusion reactor safety;
neutron flux;
nuclear engineering computing;
radiology;
shielding;
FAST design;
FISPACT code;
Fusion Advanced Studies Torus;
MCNP5;
Monte Carlo calculations;
activation analysis;
divertor;
neutron emissivity source;
neutron fluxes;
neutronic analysis;
nuclear heating calculations;
radiological safety assessment;
shielding analysis;
FAST;
activation;
neutronics;
64.
Development of the high speed pellet injector for ignitor
机译:
用于点火器的高速颗粒注射器的开发
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor ignition;
plasma radiofrequency heating;
ENEA;
ICRF heating;
Oak Ridge National Laboratory;
fusion heating rate;
high speed pellet injector;
ignitor experiment;
propellant gas removal system;
reactor design;
tokamak;
two-stage pneumatic injector;
Ignitor;
pellet injector;
two-stage gun;
65.
NCSX Trim Coil design
机译:
NCSX修剪线圈设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
coils;
eddy currents;
fusion reactor design;
nuclear power stations;
stellarators;
stress analysis;
thermal analysis;
NCSX Trim coil design;
National compact stellarator experiment;
Oak Ridge National laboratory;
Princeton plasma physics laboratory;
fusion power plants;
magnetic materials;
positioned modular coils;
stellarator design;
toroidal flux;
trim coil mechanical design;
Error Correction Coils;
Fusion;
Magnets;
NCSX;
PPPL;
Trim Coils;
66.
Ramp-up of CHI initiated plasmas on NSTX
机译:
Chi启动了奇数的升压在nstx上
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
discharges (electric);
fusion reactor ignition;
fusion reactor instrumentation;
plasma beam injection heating;
National Spherical Torus;
current drive;
inductive transformer;
plasma current;
plasmas discharges;
transient coaxial helicity injection;
Coaxial Helicity Injection;
Spherical Torus;
Start-up;
67.
Recent results and planned upgrades for the DIII-D Tokamak
机译:
最近的结果和DIII-D Tokamak的计划升级
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor operation;
plasma heating;
plasma instability;
plasma radiofrequency heating;
DIII-D plasma control system;
DIII-D tokamak;
ECH power;
ITER operating scenarios;
auxiliary heating systems;
neutral beam injectors;
noninductive current drive;
plasma disruptions;
DIII-D;
recent results;
tokamak;
upgrades;
68.
An intermediate power amplifier upgrade for 40 to 80 Mhz for the alcator C-Mod ICRF transmitters
机译:
用于Alcator C-Mod ICRF发射器的中间功率放大器升级40至80 MHz
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
fusion reactor operation;
plasma radiofrequency heating;
power amplifiers;
transmitters;
vacuum tubes;
Alcator C-Mod;
ICRF operations;
frequency 40 MHz to 80 MHz;
power amplifier;
radio frequency;
solid state broadband amplifier;
tunable transmitters;
vacuum tube amplifiers;
69.
Conceptual engineering method for attenuating He ion interactions on first wall components in the Fusion Test Facility (FTF) employing a low-pressure noble gas
机译:
概念工程方法,用于在融合试验设施(FTF)中的第一墙组件上衰减HE离子交互的方法
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
fusion reactor targets;
test facilities;
IFE reactor design;
conceptual engineering method;
detonation energetic helium ion interaction;
first wall components;
fuel reprocessing;
fusion test facility;
low-pressure noble gas shield;
magnetic intervention;
pulse power operation;
target chamber;
Direct Drive;
First Wall;
Laser Fusion;
Shield Gas;
70.
Tritium transport finite element modeling tools for breeding blanket design
机译:
氚运输有限元繁殖毯设计的有限元建模工具
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
finite element analysis;
fusion reactor blankets;
fusion reactor design;
fusion reactor fuel;
fusion reactor theory;
permeability;
tritium handling;
1D geometry;
Cast3M-based code;
ITER QA pedigree;
TMAP7 tool;
breeding blanket design;
fuel supply;
multidimensional calculation;
permeation process;
tritium transport finite element modeling;
Breeding Blanket;
Diffusion;
Permeation;
Tritium;
71.
Nuclear heating in critical components of alternative ITER first wall attachment mechanism
机译:
替代磨练第一壁附件机构的关键部件中的核加热
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
chromium alloys;
fusion reactor ignition;
fusion reactor materials;
iron alloys;
melting;
nickel alloys;
plasma heating;
stainless steel;
thermal conductivity;
3D nuclear analysis;
DAG-MCNP5;
FeCrCJk;
Inconel-718 yoke pin;
alternative ITER first wall attachment mechanism;
copper yoke;
critical components;
nuclear heating;
shield attachment mechanism;
stainless steel bolts;
3-D nuclear analysis;
Monte Carlo;
72.
Design and commissioning of the MAST neutral beam power supplies for the long pulse beam upgrade
机译:
用于长脉冲梁升级的桅杆中性光束电源的设计与调试
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor operation;
plasma beam injection heating;
MAST neutral beam power supply design;
Mega Amp Spherical Tokamak;
PINI grids;
beam extraction;
beam voltage;
current 65 A;
deuterium neutral beam power;
long pulse beam upgrade;
long pulse plasma heating;
neutral beam heating system;
plasma characteristics;
positive ion neutral injectors;
voltage 75 kV;
Neutral Beam Injection;
Plasma Heating;
Power Supplies;
73.
Emergency draining of a HCLL TBM under the influence of a strong magnetic field: First estimates
机译:
HCLL TBM紧急排放在强磁场影响下的影响:首先估计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor blankets;
fusion reactor design;
helium;
lead alloys;
liquid metals;
lithium alloys;
magnetic fields;
plasma magnetohydrodynamics;
European liquid metal test blanket module;
HCLL TBM;
ITER;
Lorentz forces;
MHD resistance;
PbLi;
breeder units;
helium cooled lead lithium blanket;
liquid metal;
plasma-confining magnetic field;
74.
He-cooled divertor for DEMO: Technological studies and experimental verification of the design
机译:
他冷却的偏移者进行演示:技术研究和设计的实验验证
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor divertors;
stainless steel;
tungsten;
DEMO design;
EU power plant;
FeCrCJk;
TSEFEY facility;
W;
helium impingement jets;
helium-cooled divertor;
mass flow rate distribution;
prototypical tungsten mock-ups;
tungsten tile;
HHF tests;
high-temperature brazing;
tungsten manufacture;
75.
Electromagnetic analysis of forces and torques on the ITER shield modules due to plasma disruption
机译:
由于等离子体中断,磨损器屏蔽模块上的力量分析和扭矩
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor theory;
ITER shield module;
OPERA-3d software;
electromagnetic analysis;
plasma disruption;
ITER;
component;
eddy-current analysis;
electromabnetic force computation;
76.
Cold test facility for the ITER central solenoid coils
机译:
浸泡中央电磁线圈的冷测试设施
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
magnets;
solenoids;
Florida State University;
ITER central solenoid coils;
ITER domestic agencies;
Oak Ridge National Laboratory;
United States ITER Project Office;
central solenoid magnet system;
cold-testing magnets;
77.
Safety related R#x00026;D for the ITER baseline design
机译:
安全相关R&D,用于ITER基线设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
fusion reactor safety;
radioactive waste;
research and development;
tritium;
tritium handling;
ITER baseline design;
fuel cycles;
fusion devices;
reactor operation;
safety;
tritium laboratories;
waste management;
ITER;
Ramp;
#x00026;
D;
fusion;
78.
Development of joining processes and fabrication of US first wall qualification mockups for ITER
机译:
开发联合过程和制造美国第一墙资格模型的磨损
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
beryllium;
chromium alloys;
copper alloys;
fracture;
fusion reactor materials;
joining processes;
stainless steel;
tensile strength;
zirconium alloys;
Be-CuCrZr-FeCrNiCJk;
ITER;
PMTF heat flux testing;
US party team first wall qualification mockup;
mechanical properties;
microstructural characterization;
tensile fracture;
First Wall Qualification Mockup;
HIP bonding;
component;
79.
An overview of the iter in-vessel coil systems
机译:
镜头内线圈系统的概述
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
coils;
fusion reactor divertors;
melting;
plasma impurities;
plasma instability;
water;
ELM mitigation;
ITER;
IVC;
RWM control;
divertor surface;
edge localized modes;
erosion;
in-vessel coil systems;
pellet;
plasma impurity;
resonant magnetic perturbation;
unstable resistive wall modes;
80.
Development of closed-cell syntactic SiC-foam for Flow Channel Inserts
机译:
流动通道插入件闭孔句法SiC - 泡沫的开发
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
ceramics;
filled polymers;
fusion reactor materials;
materials preparation;
polymer foams;
silicon compounds;
wide band gap semiconductors;
ITER;
SiC;
closed-cell syntactic foam;
flow channel inserts;
matrix material;
polymer-base foams;
potential material;
size distribution;
Syntactic Foam;
81.
Siting evaluations for the ignitor fusion experiment: Preliminary radiological assessments
机译:
点火器融合实验的选址评估:初步放射性评估
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor ignition;
fusion reactor operation;
fusion reactor safety;
plasma heating;
Caorso Site;
accidental analysis;
deuterium-tritium plasma;
high-magnetic field tokamak;
ignitor fusion experiment;
northern Italy;
nuclear power reactor;
plasma burning conditions;
probabilistic safety assessment;
radiological assessments;
radiological impact analyses;
reactor operation;
Ignitor;
radiological impact;
siting;
82.
Target steering and electrostatic acceleration for IFE
机译:
IFE的目标转向和静电加速度
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
electrodes;
electrostatic accelerators;
fusion reactor targets;
IFE;
Inertial Fusion Energy;
accelerating electrodes;
electrostatic accelerator;
steering electrodes;
target steering;
vacuum acceleration;
Electrostatic acceleration;
Steering;
Target injection;
83.
A novel demountable TF joint design for low aspect ratio spherical torus tokamaks
机译:
用于低宽高比球形圆环托克马克的新型可拆卸的TF联合设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
current density;
fusion reactor design;
fusion reactor ignition;
magnetic forces;
plasma toroidal confinement;
copper TF system conductors;
demountable TF joint design;
demountable electrical joints;
electrical current density;
magnetic force;
mechanical stress;
radial conductors;
spherical torus tokamaks;
84.
ITER storage and delivery system R#x00026;D in Korea
机译:
韩国的迭代存储和交付系统研发
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
calorimetry;
cobalt alloys;
fusion reactor design;
fusion reactor instrumentation;
fusion reactor materials;
radioactive waste storage;
tritium handling;
zirconium alloys;
ITER delivery system;
ITER storage;
ITER tritium plant;
ZrCo beds;
ZrCoJk;
benchmarking mock-up calorimeter;
in-bed calorimetry;
tritium storage;
SDS;
ZrCo Bed;
simulator, SPOVE;
storage and delivery system;
tritium;
85.
Mechanical design of the NSTX Liquid Lithium Divertor
机译:
NSTX液态锂偏转器的机械设计
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
copper;
evaporation;
fusion reactor design;
fusion reactor divertors;
lithium;
plasma diagnostics;
plasma toroidal confinement;
stainless steel;
Cu;
FeCrCJk;
Li;
NSTX liquid lithium divertor;
fully-toroidal liquid lithium divertor;
high-power magnetic confinement device;
lithium evaporation;
mechanical design;
plasma-facing surface;
porous molybdenum layer;
temperature 200 degC to 400 degC;
thick copper substrate;
thin stainless steel layer;
component;
formatting;
style;
styling;
86.
Embedding linux On FPGA: An application on a real-time neutron/gamma Discrimination system for fusion devices
机译:
在FPGA上嵌入Linux:用于融合装置的实时中子/伽马辨别系统的应用
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Linux;
field programmable gate arrays;
fusion reactor materials;
high energy physics instrumentation computing;
local area networks;
FPGA-embedded processor;
Frascati neutron/gamma digital pulse shape discrimination system;
fusion devices;
hardware parameters;
real time data distribution;
software programs;
standard Ethernet network;
FPGA;
component;
embedded systems;
neutron-gamma discrimination;
real-time;
87.
Advancements in electrical insulations for fusion devices
机译:
融合设备电绝缘的进步
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
ageing;
copper;
electric breakdown;
electrical resistivity;
filled polymers;
fusion reactor design;
fusion reactor materials;
glass fibre reinforced composites;
insulating materials;
aging process;
composite technology development;
copper foil-CTD 403;
cyanate ester polymer;
degradation;
dielectric breakdown strength;
drying;
electrical insulation material;
electrical properties;
glass fiber-CTD 403;
moisture resistance;
Cyanate Esters;
Fusion Materials;
Moisture;
88.
Results of Compact Stellarator engineering trade studies
机译:
紧凑型螺栓工程贸易研究结果
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
fusion reactor design;
nuclear power stations;
nuclear reactor maintenance;
stellarators;
superconducting coils;
superconducting magnets;
ARIES-CS reactor design;
NCSX;
National Compact Stellarator Experiment;
coil positioning;
compact stellarator engineering trade;
machine maintenance;
mechanical configuration;
metrology;
shaped fixed stellarator coils;
stellarator based power plant;
stellarator coil geometry;
stellarator configuration;
stellarator magnet configuration;
tight tolerances;
trim coils;
89.
Fuelling and disruption mitigation in ITER
机译:
在ITER中加油和中断缓解
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
discharges (electric);
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
plasma density;
Dlt;
subgt;
2lt;
/subgt;
gases;
ELM pacing functionality;
Hlt;
subgt;
2lt;
/subgt;
gases;
ITER tokamak operations;
discharge parameters;
disruption mitigation;
disruption mitigation system;
fuelling;
gas puffing;
pellet injection system;
plasma density control tool;
runaway electrons;
wall conditioning operation;
ELM Pacing;
Gas Injection;
ITER;
Pellet Injection;
Plasma control;
component;
90.
Overview of MAST Neutral Beam System performance
机译:
桅杆中性光束系统性能概述
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
fusion reactor design;
fusion reactor operation;
plasma diagnostics;
MAST neutral beam system;
Mega Amp Spherical Tokamak;
diagnostic capability;
reactor design;
reactor operation;
MAST;
diagnostic;
interlocks;
neutral beam;
plasma heating;
91.
Advantages of high tolerance measurements in fusion environments applying photogrammetry
机译:
应用摄影测量的融合环境中耐受测量高的优点
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
CAD;
digital photography;
fusion reactor instrumentation;
photogrammetry;
stellarators;
tolerance analysis;
welding;
CAD coordinate-based computer metrology equipment;
NCSX;
National compact stellarator experiment;
absolute distance measurement-based laser trackers;
coordinate measurement machine;
digital photographs;
fusion environments;
metrology;
multiple point measurements;
welding operations;
measurement;
92.
Thermo-mechanical analysis of a prototypical SiC foam-based flow channel insert
机译:
基于原型SIC泡沫的流动通道插入物热机械分析
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
foams;
fusion reactor blankets;
fusion reactor operation;
porous materials;
silicon compounds;
thermomechanical treatment;
FCI;
ITER;
SiC;
composite materials;
flow channel;
prototypical foam;
temperature 150 C;
test blanket module;
thermomechanical analysis;
Flow Channel Inserts;
Open-Cell Foam;
Porous;
Silicon Carbide;
93.
Description and preliminary results of a new photo detector for the DIII-D Thomson scattering diagnostic
机译:
DIII-D Thomson散射诊断的新照片探测器的描述和初步结果
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
CAMAC;
Thomson effect;
Tokamak devices;
computerised instrumentation;
data acquisition;
fusion reactor design;
integration;
nuclear engineering computing;
photodetectors;
plasma diagnostics;
preamplifiers;
DIII-D Thomson scattering diagnostic;
LeCroy FERA CAMAC gated integrator modules;
background subtraction;
bias circuits;
data acquisition system;
distribution panels;
photodetector;
preamplifier;
timing circuits;
Thomson scattering;
photo detector;
94.
Conceptual design of optical path related elements in the port plug of ITER core lidar diagnostic
机译:
光路相关元件概念设计在迭代核心激光器诊断的端口插头中
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
cooling;
fusion reactor design;
fusion reactor operation;
fusion reactor safety;
fusion reactor theory;
neutron absorption;
optical elements;
plasma diagnostics;
thermal analysis;
ITER core LIDAR diagnostics;
baking;
engineering conceptual design;
mirror extension tube;
neutron absorption function;
neutron shielding plates;
optical labyrinth;
optical path related elements;
port plug;
post operation safety;
sputtered particles;
water-steel mixture;
95.
Three dimensional tolerance investigations on assembly of ITER vacuum vessel
机译:
浸泡真空血管组装的三维公差调查
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
coils;
fusion reactor blankets;
fusion reactor design;
fusion reactor divertors;
ELM coils;
ITER components;
ITER vacuum vessel;
US company dimensional control systems;
complex components;
integration;
manufacturing process;
port plugs;
reactor blankets;
reactor divertor;
vacuum vessel torus;
DCS tolerance study;
ITER;
Vacuum Vessel;
96.
Component design in tight areas in the cryostat of Wendelstein 7-X - configuration management and control -
机译:
WENDELSEIN 7-X - 配置管理和控制致静电晶罩的紧张区域中的组件设计 -
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
cryostats;
deformation;
electromagnetic forces;
fusion reactor design;
fusion reactor materials;
stellarators;
3D geometry;
Wendelstein 7-X stellarator;
collision free design;
component design;
configuration management;
control management;
cryostat;
magnet system;
mechanical loads;
plasma vessel;
Stellarator;
Wendelstein-7X;
component;
configuration control;
design;
reverse engineering;
97.
Combustion of hydrogen from the ITER Water Detritiation System
机译:
氢气燃烧系统燃烧氢气
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
catalysis;
combustion;
fusion reactor fuel;
fusion reactor operation;
fusion reactor safety;
nuclear reactor maintenance;
tritium handling;
water;
Hlt;
subgt;
2lt;
/subgt;
O;
ITER water detritiation system;
T;
catalyst bed;
catalytic combustion;
deuterium-tritium fusion reactions;
fusion reactor ITER;
fusion reactor maintenance;
hydrogen stream;
microchannel reactor;
nuclear fusion technology;
passive autocatalytic recombiner;
catalytic;
hydrogen;
98.
Neutronics performance parameters for the US dual coolant lead lithium ITER test blanket module
机译:
美国双冷却液引线锂磨练试验毯模块的中型性能参数
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
electrical conductivity;
fusion reactor blankets;
fusion reactor design;
fusion reactor ignition;
fusion reactor theory;
thermal conductivity;
tritium handling;
CAD models;
SiC flow channel;
US dual coolant lead lithium ITER test blanket module design;
electrical conductivities;
neutronics performance parameters;
nuclear heating;
radiation damage;
thermal conductivities;
tritium breeding ratio;
lead lithium;
test blanket;
99.
Computational study of the electromagnetic forces and torques on different ITER first wall designs
机译:
电磁力和扭矩在不同迭代第一墙体设计上的计算研究
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
eddy currents;
electromagnetic forces;
fusion reactor design;
plasma instability;
plasma-wall interactions;
torque;
ITER first wall designs;
electromagnetic analysis;
electromagnetic torques;
plasma disruption;
ITER first wall components;
component;
100.
Operation and characterization of a Water Detritiation Facility at the Tritium Laboratory Karlsruhe
机译:
Tritium实验室Karlsruhe水脱裂设施的操作与表征
会议名称:
《IEEE/NPSS Symposium on Fusion Engineering》
|
2009年
关键词:
Tokamak devices;
catalysts;
electrolysis;
fusion reactor design;
fusion reactor fuel;
fusion reactor operation;
hydrophobicity;
tritium handling;
water;
European procurement package;
Hlt;
subgt;
2lt;
/subgt;
O;
ITER water detritiation system;
T;
TRENTA3;
Tritium Laboratory Karlsruhe;
combined electrolysis-and-catalytic exchange process;
decontamination factor;
electrolyzer;
hydrophobic catalyst;
liquid phase catalytic exchange column;
operational parameter;
tritiated gas;
CECE;
ITER;
fuel cycle;
tritium;
water detritiation;
上一页
1
2
3
4
5
6
7
下一页
意见反馈
回到顶部
回到首页