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Daneshyari Energy Engineering and Power Technology Journas Latest Articles

Energy Engineering and Power Technology Research Articles

Performance of the LH antenna with carbon grill in JT-60U
Fulltext Access 5 Pages 2005
Developing the next LHCD source for Tore Supra
Fulltext Access 5 Pages 2005
Toward a LHCD system for ITER
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An n-port error model and calibration procedure for measuring the scattering matrices of lower-hybrid multijunctions
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MAST neutral beam long pulse upgrade
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Progress of the KSTAR ICRF components development for long pulse operation
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RF-source development for ITER: Large area H− beam extraction, modifications for long pulse operation and design of a half size ITER source
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ECH MW-level CW transmission line components suitable for ITER
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Status of the TJ-II Electron Bernstein Waves heating project
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Diagnostics of the cesium amount in an RF negative ion source and the correlation with the extracted current density
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Development of CW and short-pulse calorimetric loads for high power millimeter-wave beams
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Design of the mm-wave system of the ITER ECRH upper launcher
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First results of the Tore Supra ITER like ICRF antenna prototype
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Maintenance schemes for the ITER neutral beam test facility
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Neutral beam injection optimization at TJ-II
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140 GHz high-power gyrotron development for the stellarator W7-X
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Development of the 140 GHz gyrotron and its subsystems for ECH and ECCD in TEXTOR
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Design of cryosorption pumps for TEST BEDS of ITER relevant Neutral Beam Injectors
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Subject Index of Volume 235
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The PROTO-SPHERA load assembly
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The WENDELSTEIN 7-X mechanical structure support elements: Design and tests
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Magnum-psi, a plasma generator for plasma-surface interaction research in ITER-like conditions
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Comparison of strategies and regulator design for active control of MHD modes
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Study on a system frequency response model for a large industrial area load shedding
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Logarithmic barrier-augmented Lagrangian function to the optimal power flow problem
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System reliability worth assessment at a midwest utility-survey results for residential customers
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DIII-D integrated plasma control tools applied to next generation tokamaks
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Evolution of the DINA-CH tokamak full discharge simulator
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Real-time control environment for the RFX experiment
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A fast and versatile interlock system
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A new controller for the JET error field correction coils
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Using Real Time Workshop for rapid and reliable control implementation in the Frascati Tokamak Upgrade Feedback Control System running under RTAI-GNU/Linux
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The system architecture of the new JET Shape Controller
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Status of the new ECRH system for ASDEX Upgrade
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XSC plasma control: Tool development for the session leader
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Plasma feedback controller reorganisation for ASDEX Upgrade's new discharge control and data acquisition system
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The Alcator C-Mod lower hybrid current drive experiment transmitter
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Design of an ultra-broadband single-disk output window for a frequency step-tunable 1 MW gyrotron
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The LHCD launcher for Alcator C-Mod-Design, construction, calibration and testing
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Tests of load-tolerant external conjugate-T matching system for A2 ICRF antenna at JET
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Neutronic analysis of ITER neutral beam test bed
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A review of JET neutral beam system performance 1994-2003
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Digital mock-up design of the remote steerable ITER ECRH launching system
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An alternative ECRH front steering launcher for the ITER upper port
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Applied technologies and inspections for the W7-X pre-series target elements
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Tiles chamfering and power handling of the MK II HD divertor
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Thermal and mechanical analysis of the EAST plasma facing components
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Hot radial pressing: An alternative technique for the manufacturing of plasma-facing components
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The use of copper alloy CuCrZr as a structural material for actively cooled plasma facing and in vessel components
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Preliminary analysis on a liquid lithium limiter in capillary porous system (CPS) configuration in view of a “litization” experiment on FTU tokamak
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The new electron beam test facility JUDITH II for high heat flux experiments on plasma facing components
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Steady state and transient thermal-hydraulic analyses on ITER divertor module
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An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD
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Thermal modeling of W rod armor
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Towards the development of workable acceptance criteria for the divertor CFC monoblock armour
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Development of a copper alloy to beryllium HIP bonding technology for the ITER first wall
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Structural and fracture mechanics analysis of ITER toroidal field coil
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Plasma sprayed tungsten-based coatings and their performance under fusion relevant conditions
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Simulation of multi-atomic interactions in H-O-W system with the MD code CADAC
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Erosion of macrobrush tungsten armor after multiple intense transient events in ITER
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Development of an original active thermography method adapted to ITER plasma facing components control
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Management of a water leak on actively cooled fusion devices
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Status of He-cooled divertor development for DEMO
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Design progress of the ITER vacuum vessel and ports
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Manufacture of the vacuum vessels and the ports of Wendelstein 7-X
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Assessment of a cooperative maintenance scheme for ITER divertor cooling pipes
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Design and thermal performance of an improved mechanically attached module for divertor plate of LHD
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Operational experience feedback in JET Remote Handling
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ITER articulated inspection arm (AIA): R&d progress on vacuum and temperature technology for remote handling
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Generic control system design for the Cassette Multifunctional Mover and other ITER remote handling equipment
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Development of the plasma facing components for the dome-liner component of the ITER divertor
Fulltext Access 6 Pages 2005
Study on model of onset of nucleate boiling in natural circulation with subcooled boiling using unascertained mathematics
Fulltext Access 6 Pages 2005
EMI on diagnostics and control circuits due to switching power supplies
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Quench current measurement and performance evaluation of the EAST toroidal field coils
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130 kV 130 A high voltage switching mode power supply for neutral beam injectors-Control issues and algorithms
Fulltext Access 6 Pages 2005
Manufacture of blanket shield modules for ITER
Fulltext Access 6 Pages 2005
Design, performance and construction of a 2 MW ion beam test facility for plasma facing components
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Spectroscopic studies of homogeneous thin carbon erosion films on mirrors and flakes with a high deuterium content formed in tokamak T-10
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Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests
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Critical heat flux testing on screw cooling tube made of RAFM-steel F82H for divertor application
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The ITER neutral beam test facility: Designs of the general infrastructure, cryosystem and cooling plant
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ITER-like PAM launcher for Tore Supra's LHCD system
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The JET-Enhanced Performance programme: More heating power and diagnostic capabilities in preparation for ITER
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Selection of design solutions and fabrication methods and supporting R&D for procurement of ITER vessel and FW/blanket
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Dynamic identification of the hydraulic Maestro manipulator-Relevance for monitoring
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Analyses of the ITER vacuum vessel with the use of a new modelling technique
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Main design features and challenges of the ITER-like ICRF antenna for JET
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The test of a PAM launcher on FTU: The first step toward the LHCD launcher for ITER
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Status of the 140 GHz, 10 MW CW transmission system for ECRH on the stellarator W7-X
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RF tests of the electrical insulations for the toroidal structures of RFX
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Tore Supra ITER-like antenna characterization by FEM analysis
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Development of a full scale ECRH mm-wave launching system mock-up for ITER
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Development of reliable diamond window for EC launcher on fusion reactors
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The ASDEX Upgrade ICRF system: Operational experience and developments
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Manufacturing technology development for vacuum vessel and plasma facing components
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Manufacturing of the Wendelstein 7-X divertor and wall protection
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Recent progress of negative ion based neutral beam injector for JT-60U
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The need for fusion
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Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor
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Crack propagation behavior by thermal fatigue around DSCu/SS316 HIP bonded interface
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