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Daneshyari Civil and Structural Engineering Journas Latest Articles

Civil and Structural Engineering Research Articles

The design of quench protection of EAST toroidal field power supply system
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Advanced tools for enhancing control room collaborations
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Status of the control system on the National Spherical Torus Experiment (NSTX)
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Digital real-time plasma control system for Alcator C-Mod
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Development review of transient recorders with onboard isolation on JET
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A unified real-time control and data acquisition hardware platform
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Integration of MDSplus in real-time systems
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First operation of RFX-mod real-time control system
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Using the network as bus system for long discharge data acquisition and data processing
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Status and prospect of JT-60 plasma control and diagnostic data processing systems for advanced operation scenarios
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Control, data acquisition, and remote participation for fusion research
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Upgrading program for improving the cryogenic stability of LHD helical coils by lowering the operating temperature
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Flashover characteristics along spacer at cryogenic temperature influenced by minute gaps between spacer and electrode
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Overview of the TJ-II remote participation system
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Comparison of avalanche-like quenches between NbTi and Nb3Sn cables
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Application of prebending effect to high strength Nb3 Sn strands
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Optimization of a conduction-cooled LTS pulse coil
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RHQT JR Nb3Al conductors developed for nuclear fusion devices
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Stress–strain behavior on tensile and low cycle fatigue tests of JLF-1 steel at elevated temperature in vacuum
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Structural stability and self-healing capability of Er2O3 in situ coating on V–4Cr–4Ti in liquid lithium
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Real-time impedance matching system using liquid stub tuners in ICRF heating
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Ion cyclotron conditioning with strong magnetic field in LHD
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Long pulse operation of 170 GHz ITER gyrotron by beam current control
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Development of a system code for an IFE reactor and investigation of a design regime for a dry wall chamber concept
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Possibility of tritium self-sufficiency in low aspect ratio tokamak reactor with the outboard blanket only
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Improvement of compatibility of advanced ferritic steels with super critical pressurized water toward a higher thermally efficient water-cooled blanket system
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Fuzzy optimization of cold-formed steel sheeting using genetic algorithms
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Optimal shakedown design of metal structures under stiffness and stability constraints
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Analysis of longitudinal shear behaviour for composite steel and concrete slabs
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Behaviour of semi-rigid steel beam-to-beam joints under bending and axial forces
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The structural safety of connections with fillet welds
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Stress/strain state investigations for extreme points of thin wall cylindrical tanks
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Neutronics analysis for a compact reversed shear tokamak CREST
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Preliminary design for a China ITER test blanket module
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Structural analysis and manufacture for the vacuum vessel of experimental advanced superconducting tokamak (EAST) device
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Application of imaging plate technique for separate detection of 3H and 14C
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Fatigue crack growth behavior and microstructure of reduced activation ferritic/martensitic steel (JLF-1)
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An evaluation of helium embrittlement resistance of reduced activation martensitic steels
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Update of ITER 3D basic neutronics model with MCAM
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Characterizations of Li2TiO3 prepared by a solution combustion synthesis and fabrication of spherical particles by dry-rolling granulation process
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Microstructural evolution during creep of 9Cr-ODS steels
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Surface reaction of titanium beryllide with water vapor
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Interaction between hydrogen isotopes and damaged structures produced by He+ implantation in SiC
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Small specimen test technique for evaluating fracture toughness of blanket structural materials
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Research and development of low activation V-based superconducting materials based on the requirement for an advanced fusion reactor application
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Effect of electron irradiation on microstructural damage in the welded portion of a SUS304 weldment
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Influence of blistering on deuterium retention in tungsten irradiated by high flux deuterium 10–100 eV plasmas
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The in situ growth of Er2O3 coatings on V–4Cr–4Ti in liquid lithium
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Mechanical properties of friction welds of RAFs (JLF-1) to SUS304 steels as measured by the acoustic emission technique
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Effect of a SiC whisker formation on the densification of Tyranno SA/SiC composites fabricated by the CVI process
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Dynamic erosion and deposition on carbon and tungsten due to simultaneous bombardment with deuterium and beryllium ions in plasmas
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Recent progress of ITER FW/blanket design and preparations for fabrication
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ITER first wall Module 18—The US effort
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Ablation of hydrogen-implanted graphite target using pulsed laser beam
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Hydrogen permeability and erosion behavior of W–Pd bimetallic systems
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High flux ion beam acceleration at the 100-eV level for fusion plasma facing material studies
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EU R&D on the ITER First Wall
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He-cooled divertor for DEMO: Experimental verification of the conceptual modular design
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Effect of low energy helium irradiation on mechanical properties of 304 stainless steel
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Helium irradiation effects for deuterium retention in boron coating films
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Hydrogen retention and depth profile in divertor tiles of Jt-60 exposed to hydrogen discharges
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Notch toughness evaluation of diffusion-bonded joint of alumina dispersion-strengthened copper to stainless steel
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Investigation of the impact of fabrication methods on the microstructure features of W-components of a He-cooled divertor
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Thermal conductivity of compressed beryllium pebble beds
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Erosion of carbon deposition layer by hydrogen RF plasma
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Simulation of redeposition patterns of hydrocarbons released from carbon target in divertors
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Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket
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Material probe analysis of boronized wall in LHD
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Progress of plasma surface interaction study on low activation materials
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Critical heat flux loading experiments on CVD-W coating in the TEXTOR tokamak
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Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour
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Applicability of β-ray-induced X-ray spectrometry to in situ measurements of tritium retention in plasma-facing materials in ITER
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JET contributions to ITER technology issues
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Behavior of actively cooled mock-ups with plasma sprayed tungsten coating under high heat flux conditions
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Integration of an advanced He-cooled divertor in a DEMO-relevant tokamak geometry
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Design approach for the main ITER test blanket modules for the EU helium cooled lithium–lead blankets
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Development of CAD/MCNP interface program prototype for fusion reactor nuclear analysis
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Development of three-dimensional neutronics calculation system for design studies on helical reactor FFHR
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Numerical study of magnetic field configuration for FFHR from a viewpoint of divertor and edge field structure
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Burning plasma simulation of TR-1 tokamak and HR-1 helical reactors
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Removal of cold alpha particles from helical device for fusion
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Aspect ratio dependencies of D–3He fueled tokamak reactors
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Conceptual design activities of FDS series fusion power plants in China
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The European power plant conceptual study: Helium-cooled lithium–lead reactor concept
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Performance of fueling pellet injectors for the large helical device
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Cryogenic pellets with controlled length for pellet ablation studies
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CFD modeling of ITER cable-in-conduit superconductors: Part II. Effects of spiral geometry on the central channel pressure drop
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Design and validation of breeder unit of helium-cooled pebble bed blanket for demo fusion reactor
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U.S. contributions to ITER
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Control of nitrogen concentration in liquid lithium by iron–titanium alloy
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Solid breeder test blanket module design and analysis
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Topology of compressed pebble beds
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Determination of hydrogen solubility in lead lithium using sole device
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Reactivity of H2O gas with the surface of polycrystalline Li2O pellet
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Experimental study of the interaction of ceramic breeder pebble beds with structural materials under thermo-mechanical loads
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Study of heat transfer enhancement/suppression for molten salt flows in a large diameter circular pipe: Part I: Benchmarking
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Tritium release from neutron-irradiated Li2O: Transport in porous sintered pellets
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Interactions between molten Flibe and metallic Be
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Dynamic amplification of reaction forces in the blanket module attachment during plasma disruption of ITER
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Breeder foam: an innovative low porosity solid breeder material
Fulltext Access 6 Pages 2006
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