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SOFT 2018
16–21 Sept 2018
Giardini Naxos
Europe/Rome timezone
Overview
Scientific Programme
Timetable
Contribution List
Book of Abstracts
Material Package
Added Since
Include only attachments uploaded after this date
Include
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Everything
Specific sessions
Specific contributions
Specific days
Sessions
*
I2.1
I2.3
I6.1
I6.2
Gala Dinner
I6.3
P3
O2.B
I3.3
O1.A
I4.1
I4.2
I4.3
O4.A
O4.B
O4.C
O5.A
O5.B
O5.C
Closing
O1.B
O3.A
O2.C
SOFT Innovation Prize
P4
O3.C
I3.2
I3.1
Opening Ceremony
P2
P1
I5.2
I5.1
I5.3
O2.A
O1.C
O3.B
Social Tour
I2.2
I6.4
I6.5
I6.6
Temporary
Welcome Reception
I1.1
Concert
Include materials from selected sessions
Contributions
*
3D Tritium Transport Model at Breeder Unit Level for WCLL Breeding Blanket (in session "P1")
10 MW FULGOR power supply performance tests and overview of test facility components (in session "P1")
14 MeV neutron streaming calculations for JET-like maze entrance using TRIPOLI-4 Monte Carlo code (in session "P1")
A 15 T large aperture dipole for testing fusion and accelerator superconducting samples (in session "P1")
A European design proposal on the ITER ELM-Coil Power Supply optimized for ELM mitigation and RWM stabilization (in session "P1")
A horizontal powder injector for W7-X (in session "P1")
A new generation of power supplies for pulsed loads (in session "O2.A")
A novel code for the simulation of plasma equilibrium and evolution (in session "P1")
A preliminary assessment of MCNP unstructured mesh integration in the ITER neutronic model (in session "P1")
A PROs-industry joined effort for the ITER construction: evaluating the impact (in session "I6.5")
A smart architecture for the DEMO fuel cycle (in session "I4.2")
A two colors interferometer for PROTO-SPHERA experiment (in session "P1")
Activation foil measurements at JET in preparation for D-T plasma operation (in session "P1")
Alloy element induced vacancy clustering in W-Re/Ta material (in session "P1")
An enhanced near-term HCPB configuration as driver blanket for the EU DEMO (in session "O2.C")
An Optimization Study for Shielding Design of D-D and D-T Neutron Generators (in session "P1")
An Overview of the EU Breeding Blanket Strategy as Integral Part of the DEMO Design Effort (in session "I6.1")
Analyses of the influence of the recycling coefficient on He confinement in DEMO reactor (in session "P1")
Analysis of an actively-cooled coaxial cavity in a 170 GHz, 2 MW gyrotron using the multi-physics tool MUCCA (in session "P1")
Analysis of inner divertor materials of JET C-wall and ILW from viewpoint of spectrometric investigations (in session "P1")
Analysis of technical and economic parameters of fusion power plants in future power systems (in session "P1")
ANITA-NC: a Code System for Modelling Material Activation Induced by Neutral or Charged Particles (in session "P1")
Assembly and final dimensional inspection at factory of the JT60-SA Cryostat Vessel Body Cylindrical Section (in session "P1")
Assessment of controllers and scenario control performance for ITER first plasma (in session "P1")
Assessment of Critical Heat Flux margin on the Tungsten monoblock design of ITER Divertor (in session "O3.A")
Assessment of environmental effects on the ITER FOCS operating in reflective scheme with Faraday mirror (in session "P1")
Automation of upgraded NBI cooling water system (in session "P1")
CFETR Integration Design Platform: overview and recent progress (in session "O3.C")
Characteristics and Experiment Measurement of Cascaded Plasma In Linear Plasma Devices (in session "P1")
Characterization of modified Be13Zr beryllide as advanced neutron multiplier (in session "P1")
Characterization of the SPIDER Cs oven prototype in the CAesium Test Stand for the ITER HNB negative ion sources (in session "P1")
Combining research with safety: the Wendelstein 7-X video diagnostic system (in session "O2.B")
Completion of the JT-60 SA Toroidal Field coils tests in the Cold Test Facility (in session "O3.B")
Conceptual design of a Neutral Beam Heating system for DTT (in session "P1")
Conceptual Design of a Toroidal Field Coil using HTS CrossConductor (in session "P1")
Conceptual design of the COMPASS-U tokamak (in session "O1.A")
Conceptual studies on optical diagnostic systems for plasma control on DEMO (in session "P1")
Contribution to safety analyses of DEMO HCPB using AINA code (in session "P1")
Convective Baking Test of the ITER Lower Port for Factory Acceptance (in session "P1")
Cooling optimization of the electron cyclotron upper launcher blanket shield module (in session "P1")
Critical Design Issues in DEMO and Solution Strategies (in session "P1")
Decontamination tests of dust under load for the ITER blanket remote handling system (in session "P1")
Deep Learning: Towards Autonomous Remote Maintenance (in session "O1.C")
Deformation and fracture behavior of the ODS-Cu/W joint fabricated by the improved brazing technique (in session "P1")
Delphi Exercise on the possible role of fusion energy in the global energy system (in session "P1")
Design and analysis of robot for the maintenance of divertor in DEMO fusion reactor (in session "P1")
Design and Countermeasures against Cavitation in a Downstream Conduit of the Liquid Lithium Target for International Fusion Materials Irradiation Facility (in session "P1")
Design and development of the mechanical support structure for ITER in-vessel magnetic sensors (in session "P1")
Design and development of the mechanical support structure for ITER in-vessel magnetic sensors (in session "P1")
Design and measuring performance of the ITER plasma position reflectometer in-port-plug antennas. (in session "P1")
Design and preliminar operation of a laser absorption diagnostic for the SPIDER RF source (in session "P1")
Design and preliminar operation of a laser absorption diagnostic for the SPIDER RF source. (in session "P1")
Design and preliminary testing of a sieve tray column for PbLi purification (in session "P1")
Design and simulation of a cascaded four-quadrant 24- pulse converter based on 6-phase pulsed motor-generator (in session "P1")
Design concept and thermal-structural analysis of a high power reflective mm-wave optical mirror (M2) for the ITER ECH Upper Launcher (in session "P1")
Design Criteria of the Electrical Power Supply for Lithium Loop System of DEMO-Oriented NEutron Source (DONES) plant. (in session "P1")
Design evolution of the diamond window unit for the ITER EC H&CD upper launcher (in session "P1")
Design of High Current Busbar Contact Connection for ITER Poloidal Field Converter (in session "P1")
Design of scalable vacuum pump to validate sintered getter technology for future NBI application (in session "P1")
Design of the ITER EC upper launcher nuclear shielding (in session "P1")
Deuterium retention behavior in tungsten irradiated with neutron under divertor operation temperature (in session "P1")
Development and qualification of ITER current lead electrical insulation (in session "O3.B")
Development of an electrochemical sensor for hydrogen detection in liquid lithium for IFMIF-DONES (in session "P1")
Development of data acquisition and control system for quasi-2D turbulent electrolyte flow experiment (in session "P1")
Development of Experimental Helium Cooling Loop (EHCL) for testing nuclear fusion blanket components (in session "P1")
Development of HINEG and its experimental campaigns (in session "O1.A")
Development of medium size DOME & reflector plate for ITER like tokamak application (in session "P1")
Development of Pb-16Li technologies for DEMO Reactor (in session "O2.C")
Development of plasma control algorithm design via machine learning (in session "P1")
Development of power combination system for high-power and long-pulse ICRF heating in LHD (in session "P1")
Development of reliable tooling and processes for remote maintenance of ITER cooling water connections (in session "P1")
Development of Winding Technology for ITER PF6 Double Pancakes (in session "P1")
Diagnostics for plasma control - from ITER to DEMO (in session "I6.4")
Digital valve system for ITER remote handling – design and prototype testing (in session "O1.C")
Digital valve system for ITER remote handling – design and prototype testing (in session "P1")
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence (in session "P1")
Effect of coil configuration parameters on the mechanical behavior of the superconducting magnet system in the helical fusion reactor FFHR (in session "P1")
Effect of plasma screening on pumping efficiency in the DEMO divertor (in session "P1")
Effects of process variables on microstructure and tensile properties of friction stir welded ARAA (in session "P1")
EHF FW panel for ITER BM with mechanical attachment of the plasma-facing components (in session "P1")
Electromagnetic FEM studies of disruptions and engineering consequences for the power supply and coils design of planned upper divertor at ASDEX Upgrade (in session "O1.A")
Electromagnetic modelling and design of DEMO and disruption location prediction (in session "P1")
EM analyses on the 55.NE.V0 loom system and attached components (in session "P1")
Endoscopes for observation of plasma-wall interactions in the divertor of Wendelstein 7-X (in session "P1")
Engineering and integration design risks arising from advanced magnetic divertor configurations (in session "O1.C")
Enhanced Droplet Control for the Fabrication of Ceramic Breeder Pebbles (in session "P1")
Environmenta,l steam-ingress and gamma irradiation tests for optical materials candidates for ITER equatorial-Vis/IR-WAVS diagnostic (in session "P1")
Equilibrium evaluation for OP1.2a Wendelstein 7-X experiment programs (in session "P1")
EUROfusion Plasma EXhaust (PEX) strategy on upgrades to European tokamaks and PFC test facilities (in session "P1")
European DEMO divertor R&D activities: loads, design concepts and technologies (in session "P1")
European Integrated Programme in support to ITER: Overview of JET and Medium Size Tokamak results (in session "I3.1")
European Materials Development: Results and Perspectives (in session "I5.2")
European roadmap to fusion energy (in session "I2.2")
Examination of ITER Central Solenoid prototype joints (in session "P1")
Examination of ITER Central Solenoid prototype joints (in session "P1")
Experimental analysis of dummy load prototype for ITER coil power supply system (in session "P1")
Experimental and numerical studies on a gas flowing calorimetry for tritium accountability (in session "P1")
Experimental evaluation of wall shear stress in double contraction nozzle for structural soundness evaluation for liquid Li target of intense fusion neutron source (in session "P1")
Experimental investigation on the interruption performance of a switch based on artificial current zero (in session "P1")
Experimental refutation of the deuterium permeability in vanadium, niobium and tantalum (in session "O1.B")
Experimental study on MHD effect of liquid metal sheath jet for the liquid metal divertor REVOLVER-D (in session "O3.A")
Experimental tritium activities in support to tokamak operation and safety (in session "O3.C")
Experimental validation of Enhanced Heat Flux First Wall Panel Mechanical attachment system (in session "P1")
Exploration of a fast pathway to nuclear fusion: first thermomechanical considerations for the ARC reactor (in session "P1")
Exploratory risk analysis of ITER Cask & Plug Remote Handling System (in session "P1")
Exploring the upper measuring limit of pressure gauges for ITER by experimental variation of instrumental parameters (in session "P1")
Fabrication and characterization of Be12V pebbles with different diameters (in session "P1")
Fabrication Status of ITER Centrol Solenoid Modules (in session "P1")
Factory acceptance test results of ITER EU ECPS (in session "P1")
Failure and Melting of Intentionally Misaligned Tungsten Castellated Blocks under High Heat Flux (in session "P1")
Fault analysis and improved design of JET In-vessel Mirnov coils (in session "P1")
Fault analysis and overvoltage estimation in the DEMO Toroidal Field coil circuit (in session "P1")
Feasibility of fusion fuel isotope detection below 1% using Penning gauge optical spectroscopy (in session "P1")
Feasibility studies of DEMO potential waste recycling by proven existing industrial-scale processes (in session "P1")
First results from a new tritium capable ion implantation materials facility. (in session "P1")
First thermal-hydraulic and thermal-mechanical analysis of a CO2-cooled solid breeding blanket for the EU-DEMO (in session "P1")
First version of the W7-X Fast Interlock System (in session "P1")
From manufacture to assembly of the ITER central solenoid (in session "O3.B")
Full coverage infrared thermography diagnostic for WEST machine protection (in session "O2.B")
Heating and in-vessel upgrades of the TCV tokamak (in session "P1")
High particle fluence over 10^29 D+m-2 achieved in linear plasma generator Magnum-PSI (in session "O3.A")
High resolution scanning electron microscope for sequential testing and analyses of full-size PFC components of AUG (in session "P1")
High temperature brazing of tungsten with steel by Cu-based ribbon filler alloys (in session "P1")
High temperature microstructural stability of self-passivating W 10Cr-0.5Y alloy for blanket first wall application (in session "O1.C")
High Temperature Superconductors for Future Fusion Magnets and Industrial High Current Applications (in session "I4.3")
Hydraulic characterization of twin box joints for ITER magnets (in session "P1")
Hydrogen Adsorption Performance for Large-scale Cryogenic Molecular Sieve Bed (in session "O2.C")
Hydrogen isotope permeation experiment - design and first results (in session "P1")
Hydrogen isotopes distribution modeling by "FC-FNS" code in fuel systems of fusion neutron source DEMO-FNS (in session "P1")
Implementation and exploitation of jet enhancements in preparation for dt operation and next step devices (in session "O1.A")
Implementation of Laser-induced Fluorescence Diagnostics in ITER (in session "P1")
Implementing DevOps practices at the control and data acquisition system of an experimental fusion device (in session "P1")
Improving a Negative Ion Accelerator for next generation of Neutral Beam Injectors: results of QST-Consorzio RFX collaborative experiments (in session "P1")
In-box LOCA accident analysis for the European DEMO water-cooled reactor (in session "P1")
Industry Supported Improved Design of DEMO BoP for HCPB BB Concept with Energy Storage System (in session "O3.C")
Influences of fabrication conditions on hydrogen isotope retention in W coatings (in session "P1")
Innovative and emerging melting technologies for fusion power plants wastes recycling (in session "P1")
Innovative Technology for 6Li Enrichment using Electrodialysis with Lithium Ionic Conductor (in session "O1.B")
Integrated core-SOL-divertor modelling for DTT tokamak with liquid metal divertor targets (in session "P1")
Integrated current profile, normalized beta and NTM control in DIII-D (in session "O1.A")
Integrated Power Exhaust Modelling for DEMO with Lithium Divertor (in session "P1")
Interface and requirements analysis on the DEMO Heating and Current Drive system using systems engineering methodologies (in session "P1")
Interference fit process development for the ITER vacuum vessel gravity support mock-up fabrication (in session "P1")
Inverse heat flux evaluation of STRIKE data by neural networks (in session "P1")
Investigation of divertor movement during disruptions (in session "P1")
Investigation of the thermal expansion of lithium orthosilicate (in session "P1")
Isotope separation systems for a european DEMO (in session "P1")
ITER Construction and Manufacturing Progress Toward First Plasma (in session "I1.1")
ITER magnetic sensor platform engineering analyses (in session "P1")
ITER Upper Visible/Infrared Wide Angle Viewing System: I&C design and prototyping status (in session "P1")
Joints for cable-in-conduit conductors (in session "P1")
JT-60SA Program Contribution to Fusion Energy (in session "I3.2")
JT-60SA TF magnet assembly (in session "O3.B")
JT-60SA Toroidal Field coils procured by ENEA: a final review (in session "O3.B")
Kinetics of double strand breaks of DNA in tritiated water evaluated using single molecule observation method (in session "P1")
KSTAR Tokamak Visible Image sequence classification with Long-term Recurrent Convolutional Networks (in session "P1")
Laser Technology for Resident Tritium In-situ Measurement in CEPT Device (in session "P1")
Layered W-WC composites prepared by FAST (in session "P1")
Leak detection design for ITER gas injection system (in session "P1")
Lithium Loop and Purification System of DONES: Preliminary Design. (in session "P1")
Magnetic interaction between a tokamak reactor and its reinforced-concrete building (in session "P1")
Magnetically insulated baffled probe for measurements in the edge plasma of tokamaks (in session "O2.B")
Manufacturing and testing of flat type small size tungsten PFC mock-ups by HIP process (in session "P1")
Manufacturing experience and commissioning of Large Size UHV Class Vacuum Vessel for Indian Test Facility (INTF) for Neutral Beams (in session "O2.A")
Manufacturing of the first ITER Torus Cryopump (in session "O1.B")
Manufacturing, installation, commissioning and first results with LTCC-3D high-frequency magnetic sensors on TCV (in session "O2.B")
MARTe based Plasma Position Reflectometry System Integration at COMPASS Tokamak (in session "O3.C")
Material Irradiation Tests in the ITER Divertor Relevant Settings (in session "P1")
Material optimization technique to minimize radiological responses in fusion reactors (in session "P1")
Materials Development for new high heat-flux component mockups for DEMO (in session "O3.A")
Maximization of the magnetic flux generated by a DEMO CS coil using HTS conductors (in session "P1")
Measurement of neutron fluence in the High-Flux Test Module of the Early Neutron Source by an activation foils method (in session "P1")
Mechanical properties of dissimilar TIG welding for ARAA and SS316L (in session "P1")
Methodology for reverse engineering analysis of ITER as-built integrated systems (in session "O1.C")
Methods and strategies on thermal integrity management of the ITER Thermal Shield (in session "P1")
Metrology for integration and installation activities at the PRIMA Test Facility (in session "P1")
MHD mixed convection flow in the WCLL: heat transfer analysis and cooling system optimization (in session "P1")
MIMO shape control at EAST tokamak: simulations and experiments (in session "P1")
mitigation of an ingress coolant event in ITER vacuum vessel by means of steam pressure suppression (in session "P1")
Modal and response spectrum analyses of ITER divertor module (in session "P1")
Modelling of chemical vapor deposition to improve tungsten fiber reinforced tungsten composites (Wf/W) (in session "P1")
Modelling of MAST-U neutral beam re-ionisation and the impact on the beamline ducts and in-vessel components (in session "P1")
Multi-scale 3D modelling of a DEMO prototype cable from strand to full-size conductor based on X-ray tomography and image analysis (in session "O3.B")
Multidimensional linear model for disruption prediction in JET (in session "O2.B")
Multifunctional nanoceramic coatings for future generation nuclear systems (in session "O1.B")
Multiphysics Analysis of W7-X Control Coils (in session "P1")
Myth of Initial Loading Tritium-2 : Practical commissioning strategy of DEMO-Japan without external source (in session "O1.B")
Neutron diffraction measurement of residual stresses in an ITER-like tungsten-monoblock type plasma-facing component (in session "O3.A")
Neutron spectrum determination at the ITER material irradiation stations at JET (in session "O1.A")
Neutronic assessment of HCCR breeding blanket for DEMO (in session "P1")
Neutronic assessments towards a comprehensive design of DEMO with DCLL Breeding Blanket (in session "P1")
Neutronic challenges on the way from ITER to DEMO (in session "I6.3")
Neutronic effects of the ITER Upper Port environment update in C-Model (in session "P1")
Neutronics of the IFMIF-DONES irradiation facility (in session "O1.B")
Neutronics pre-analysis and the status of neutron spectrum unfolding for the development of VERDI (in session "P1")
New capabilities and upgrade path for the DIII-D neutral beam heating system (in session "O2.A")
New trends of gyrotron development at KIT: An overview on recent investigations (in session "O2.A")
Nuclear analyses of solid breeder blanket options for DEMO: status challenges and outlook (in session "P1")
Numerical study of conjugated heat transfer for DONES high flux test module (in session "P1")
On optimization of air cooling system of FDRs dissipating energy from ITER magnet coils (in session "P1")
On Structural Analyses of the ITER Vacuum Vessel Bolometer Camera Housing Conceptual Design (in session "P1")
On the path towards a Metal Foil Pump – Latest results and new experimental facility (in session "P1")
Optimal configuration of a tokamak fusion system with breeding blanket based on ITER TBM (in session "P1")
Optimal design of DMA probe for austenitic stainless steel weld of CFETR vacuum vessel (in session "P1")
Optimization and adjustment of impact set-up for testing of insulated pads of ITER blanket module connectors and first wall (in session "P1")
Optimization of GEM based detector structure aimed at plasma soft−semi hard X-ray radiation imaging (in session "P1")
Optimization of high heat flux components for DIII-D neutral beam upgrades (in session "P1")
Optimization of RFX-mod2 gap configuration by estimating the magnetic error fields due to the passive structure currents (in session "P1")
Optimization of single crystal mirrors for ITER diagnostics (in session "P1")
Overview of Beryllium and Tungsten Dust Studies in JET with the ITER-Like Wall (in session "O3.A")
Overview of the JET Operation Reliability (in session "P1")
P2.001 Modelling and experimental validation of RFX-mod tokamak shaped discharges (in session "P2")
P2.002 W7-X NBI beam dump thermocouple measurements as safety interlock (in session "P2")
P2.003 Final design of the JT-60SA pellet launching system for simultaneous density and ELM control (in session "P2")
P2.004 Three-dimensional disruption vertical stability and breakdown analysis of the Italian DTT device (in session "P2")
P2.005 Development of reactor relevant pellet launching system technology on ASDEX Upgrade (in session "P2")
P2.006 Passive control of runaway electron displacement by magnetic energy transfer in J-TEXT (in session "P2")
P2.007 Status and tasks for modernization of TRINITI site infrastructure for the Ignitor project (in session "P2")
P2.008 West Operation management Software Suite (WOSS): software assisting organization and follow-up of West operation (in session "P2")
P2.009 Design and implementation of quasi-optical components for the upgrade of the TCV EC-system (in session "P2")
P2.010 REMAINING USEFUL LIFE ESTIMATION OF CRITICAL DIII-D SUBSYSTEMS (in session "P2")
P2.011 A conceptual system design study for an NBI beamline for the European DEMO (in session "P2")
P2.012 Long-Pulse High-Power 170 GHz Absorbing Matched Load Tests and Developments (in session "P2")
P2.013 Ion Cyclotron Frequency Range Cold Magnetized Plasma Modelling in ANSYS HFSS (in session "P2")
P2.014 Design and mock-up tests of the RING photoneutralizer concept for an efficient DEMO NBI (in session "P2")
P2.015 A low power testbed for the WEST ICRF launchers and for the acceleration of their commissioning on plasma (in session "P2")
P2.016 Physics of the Traveling Wave Array for DEMO with proof of principle on WEST (in session "P2")
P2.018 Wideband polarizers switches and waveguide for Electron Cyclotron transmission lines (in session "P2")
P2.019 Experimental experience and improvement of NIO1 negative ion sources. (in session "P2")
P2.020 Maximum Likelihood Tomographic Method for the Analysis of Bolometric Measurements on JET (in session "P2")
P2.021 Safety Systems in the ITER Neutral Beam Test Facility (in session "P2")
P2.022 Initial port integration concept for EC and NB systems in EU DEMO tokamak (in session "P2")
P2.023 Conceptual study of an ICRH system for T-15MD using Traveling Wave Antenna (TWA) sections (in session "P2")
P2.024 Experimental Studies on Arc Chamber Failure Mechanisms on DIII-D Neutral Beam System (in session "P2")
P2.025 Preliminary conceptual design of the DTT EC heating system (in session "P2")
P2.026 Advanced NBI beam characterisation capabilities at the recently improved test facility BATMAN Upgrade (in session "P2")
P2.027 Equatorial electron cyclotron port plug neutronic analyses for the EU DEMO (in session "P2")
P2.028 Mechanical design of the high powered helicon antenna and strip line feed in the DIII-D tokamak* (in session "P2")
P2.029 Review of the JET ILA Scattering-Matrix Arc Detection System (in session "P2")
P2.030 The WEST plasma control system: Integration commissioning and operation on the first experimental campaigns (in session "P2")
P2.031 The dud detector: an empirically-based real-time algorithm to save neutrons and tritium during JET DTE2 (in session "P2")
P2.033 Actuator management development on ASDEX-Upgrade (in session "P2")
P2.034 Benchmarking high performance ITER CODAC data archiving system (in session "P2")
P2.035 Unified Signal Identifier for Globally Unique Signal-Addresses (in session "P2")
P2.036 The new W7-X Logbook - A Software for Effective Experiment Documentation and Collaborative Research at Wendelstein 7-X (in session "P2")
P2.037 Automatic identification of the plasma equilibrium operating space in tokamaks (in session "P2")
P2.038 Concepts of the new ASDEX-Upgrade flight simulator (in session "P2")
P2.039 Design of MITICA control and interlock systems (in session "P2")
P2.040 Influence of pellet shielding on disruption mitigation in ITER (in session "P2")
P2.041 DCS Satellite: Enhanced Plant System Integration on ASDEX Upgrade (in session "P2")
P2.042 Development of the new timing system for the ISTTOK Tokamak (in session "P2")
P2.043 The timing system of the ITER full size neutral beam injector prototype (in session "P2")
P2.044 Hazard function exploration of tokamak tearing mode stability boundaries (in session "P2")
P2.045 Upgrade of Thomson scattering system on VEST (in session "P2")
P2.046 Flexible vacuum vessel bolometer camera design in ITER to adapt to the final position of the gaps between blanket modules (in session "P2")
P2.047 JET FIR Interferometer laser operation and interlock system upgrade to an open automation system (in session "P2")
P2.048 Upgraded gamma-ray diagnostics for JET DT campaigns (in session "P2")
P2.049 A comparative study of different deconvolution methods used for reconstruction of neutron spectrum (in session "P2")
P2.050 Testing of the optical chain mock up of H-alpha and Visible Spectroscopy for ITER (in session "P2")
P2.051 Development of Thomson scattering system for VEST (in session "P2")
P2.051 Hydrogen isotope ratios measurements by Penning gauge spectroscopy of molecular Fulcher-α band (in session "P2")
P2.053 Engineering design of Wendelstein 7-X alkali metal beam diagnostic observation system (in session "P2")
P2.054 Calibration and test of the 6LiF-diamond detector for the HCPB mock-up experiment at JET (in session "P2")
P2.055 Nd:YAG Lasers for ITER Divertor Thomson scattering (in session "P2")
P2.056 On the use of rhodium mirrors for optical diagnostics in ITER (in session "P2")
P2.057 Tracking of neoclassical tearing modes in TCV using the electron cyclotron emission diagnostics in quasi-in-line configuration (in session "P2")
P2.058 Design Status of the ITER Core CXRS Diagnostic Setup (in session "P2")
P2.060 Strategy and guidelines for the calibration of the ITER radial neutron camera (in session "P2")
P2.061 The highest spatial resolution infrared thermography on ITER-like tungsten monoblocs in WEST Tokamak (in session "P2")
P2.062 Validation of neutron generator emission rate estimated based on activation measurements during in-vessel calibration of JET neutron detectors (in session "P2")
P2.063 Constraints on conceptual design of diagnostics for the high magnetic field COMPASS-U tokamak with hot walls (in session "P2")
P2.064 First heat flux decay length estimation in WEST with embedded thermal measurements (in session "P2")
P2.065 Analyses and structural integrity estimation of the Divertor Thomson Scattering system (in session "P2")
P2.066 High performance image acquisition and processing system for optical boundary reconstruction on EAST (in session "P2")
P2.067 A clustering algorithm for scintillator signals applied to neutron and gamma patterns identification. (in session "P2")
P2.068 Upgrade of scattered light collection systems for KSTAR Thomson scattering diagnostic (in session "P2")
P2.069 Estimation of neutral fluxes on the first mirror of H-alpha diagnostics in ITER (in session "P2")
P2.070 Irradiation test of fiber optics for H-alpha diagnostics in ITER (in session "P2")
P2.071 Quantitative Deuterium detection by laser-induced-breakdown-spectroscopy in ITER relevant samples (in session "P2")
P2.072 Thermo-mechanical analysis of unidirectional carbon-carbon composite for thermal imaging diagnostic of a particle beam (in session "P2")
P2.073 Study on the effects of the Signal to Noise ratio on the error in counting of the ITER Radial Neutron Camera (RNC) (in session "P2")
P2.074 Performance estimations for the ITER bolometer diagnostic (in session "P2")
P2.075 Qualification of superconducting joint for pf6 coil (in session "P2")
P2.076 Electrical performance characterization of helium inlet of the ITER PF6 coil double pancakes (in session "P2")
P2.077 TF Coil Inter-Layer Joint for EUROfusion DEMO Tokamak (in session "P2")
P2.078 AC loss assessment for fusion conductors (in session "P2")
P2.079 Design and experimental study on high current dc disconnector contact (in session "P2")
P2.080 Superconducting properties of Nb thin films prepared on different Substrates (in session "P2")
P2.081 Reactive power compensation for the pulsed power supply of ASDEX Upgrade (in session "P2")
P2.082 Test of the Insulation Mock-up’s for the ITER PF6 Coil (in session "P2")
P2.083 The starting mechanism analysis of ITER PF AC/DC in series converters (in session "P2")
P2.084 The analysis and design on transient DC over-voltage protection of ITER PF AC/DC. converter (in session "P2")
P2.085 Type Tests of Counter Pulse Circuits for the ITER Fast Discharge Units (in session "P2")
P2.086 A novel series switch module in high-voltage applications (in session "P2")
P2.087 Final design and structural analysis of ITER PF5 & 6 coil assembly tools (in session "P2")
P2.088 Influence of the flow imbalance among the cooling channel on the magnet performance (in session "P2")
P2.089 Phase-detection-based feedback control for the power supply in tearing mode control system on J-TEXT (in session "P2")
P2.090 Design of the inverter based on IEGT of acceleration grid power supply for CFETR N-NBI prototype (in session "P2")
P2.091 Design of acceleration grid power supply for CFETR negative-ion-based neutral beam injection prototype (in session "P2")
P2.092 FPGA-based interlock system for the chopper of the Linear IFMIF prototype accelerator injector (in session "P2")
P2.093 Models for the power grid load at JET (in session "P2")
P2.095 Design of the control system of acceleration grid power supply for CFETR N-NBI prototype (in session "P2")
P2.096 Receiving Inspection and Tests (RIT) of ITER Poloidal Field #4 Cryostat Feedtrough in MIFI. (in session "P2")
P2.097 Prediction of mechanical behavior of the KSTAR CS magnet based on PF coil currents (in session "P2")
P2.098 Protection system for Wendelstein 7-X superconducting magnets (in session "P2")
P2.099 ITER magnet coil power conversion building construction and AC/DC converter installation (in session "P2")
P2.100 Demonstration tests of mechanical lap and edge joints of 10-kA-class STARS conductors (in session "P2")
P2.101 Busbar Monitoring System of the ITER DC Busbars (in session "P2")
P2.102 Layered W-WC composites prepared by FAST (in session "P2")
P2.103 Synergistic effects of nitrogen seeding impurities and transient heat loads on tungsten (in session "P2")
P2.104 PFC Heat Flux Enhancement from Magnetic Field Errors in the NSTX-U Recovery Project (in session "P2")
P2.105 Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration (in session "P2")
P2.106 Heat load testing of 3D printed PFC mockups to evaluate thermo-hydraulic enhancement (in session "P2")
P2.107 Cleaning of the surface of beryllium armor tiles and beryllium products from beryllium-content particles (in session "P2")
P2.108 Fracture mechanics analyses of divertor vertical target under thermal loading conditions (in session "P2")
P2.109 EM analysis and thermal-mechanical dimensioning of First Plasma Protection Components (in session "P2")
P2.110 Thermal properties of stabilized jets for the liquid metal divertor REVOLVER-D (in session "P2")
P2.111 Thermal electromagnetic and structural analysis of gas baffles for the TCV divertor upgrade (in session "P2")
P2.112 Assessment of mechanical properties of tungsten wires for the fiber-reinforced plasma facing components (in session "P2")
P2.113 Heat transfer enhancement in MHD free-surface flow by controlling the electromagnetic force with fin structure (in session "P2")
P2.114 Effect of carbon impurity reduction on Hydrogen isotope retention in QUEST high temperature wall (in session "P2")
P2.115 Investigation of novel technology application in the high heat load components of ICRF antenna (in session "P2")
P2.116 Inverse identification of Tungsten static recrystallization kinetics (in session "P2")
P2.117 Coupled fluid-structure thermofluid-dynamic analysis of the DEMO divertor cassette body equipped with a liner (in session "P2")
P2.118 On-line measurement and removal of hydrogen isotopes in the plasma-facing material of tungsten (in session "P2")
P2.119 Hydraulic analysis of EU-DEMO divertor plasma facing components cooling circuit under nominal operating scenarios (in session "P2")
P2.120 The adhesion of tungsten dust on rough tungsten surfaces (in session "P2")
P2.121 Visualisation of subcooled pool boiling in nanofluids (in session "P2")
P2.122 China’s technological achievements on ITER enhanced heat flux first wall in the pre-PA qualification (in session "P2")
P2.123 Sublimation of advanced tungsten alloys under DEMO relevant accidental conditions (in session "P2")
p2.124 Maximizing JET divertor mechanical performance for the upcoming Deuterium-Tritium experiments (in session "P2")
P2.125 Investigation of deuterium retention in tungsten exposed to high-flux steady-state helicon plasmas (in session "P2")
P2.126 ITER-grade tungsten limiters damage under high heat flux in the T-10 tokamak (in session "P2")
P2.128 New route towards micro-structuring tungsten as stress relieving concept (in session "P2")
P2.129 Structured Cooling Channels for Intensively Heated Blanket Components (in session "P2")
P2.130 Armoring the Wendelstein 7-X divertor observation immersion tubes against NBI orbit losses (in session "P2")
P2.131 Reviewed design of the high heat flux panels for the AUG and W7-X neutral beam calorimeter (in session "P2")
P2.132 A Stereoscopic Eye-in-Hand Vision System for Remote Handling in ITER (in session "P2")
P2.134 Rescue tool for ITER Blanket Remote Handling System (in session "P2")
P2.135 Study on the Endoscopic Inspection of ITER Thermal Shield Cooling Pipes (in session "P2")
P2.136 Rationale for the selection of the operating temperature for the DEMO vacuum-vessel (in session "P2")
P2.137 Development of welding scheme for ITER Divertor Dome (in session "P2")
P2.138 Design of the K-DEMO in-vessel blanket arrangement blanket sector maintenance details and upper lever RM enclosure (in session "P2")
P2.139 Preliminary configuration of the torus vacuum pumping system installed in the DEMO lower port (in session "P2")
P2.140 Upgraded concepts and design of an in vessel inspection system for fusion reactors (in session "P2")
P2.141 Design and R&D of the second tungsten divertor of EAST (in session "P2")
P2.142 Structural assessment based on welding distortion simulation of Vacuum Vessel PS1 Jig for in-process control (in session "P2")
P2.143 The welding deformation control of large complex heavy-load vacuum Vessel port hub (in session "P2")
P2.144 FE Analyses of Eddy Currents in W7-X Plasma Vessel (in session "P2")
P2.145 Use of dimensional variation models for the PS2 Upper Subassembly of the ITER Vacuum Vessel (in session "P2")
P2.146 Kinematic calibration for a hybrid redundant robot based on Artificial Bee Colony algorithm (in session "P2")
P2.147 Key Technology Research of Electron Beam Welding in CFETR Vacuum Vessel Collar (in session "P2")
P2.148 Development of bore welding tools for ITER blanket remote maintenance (in session "P2")
P2.149 Manufacturing Study of Lower Cryostat Thermal Shield Cylinder Component for ITER Tokamak (in session "P2")
P2.150 Remote diagnostics application software for remote handling equipment (in session "P2")
P2.151 Initial integration concept of the DEMO lower horizontal port (in session "P2")
P2.152 Design and structural analysis of ITER thermal shield under transportation environment (in session "P2")
P2.153 Investigation on the in-situation pipe bending tool for the sector sub-assembly of ITER thermal shield (in session "P2")
P2.154 Welding analysis for the 1/16 VV sector of CFETR mock-up (in session "P2")
P2.155 Issues of the Vertical Blanket Segment Architecture in DEMO: current progress and resolution strategies (in session "P2")
P2.157 Operation of probe heads on the Multi-Purpose-Manipulator at W7-X (in session "P2")
P2.158 Upper port #02 and #08 structure integrity report (in session "P2")
P2.159 Electromagnetic Analyses and One-Dimensional Modeling of Piping Applied to Optimization of ITER Blanket Manifold Design (in session "P2")
P2.160 The DEMO Helium Cooled Lithium Lead “Advanced-Plus” Breeding Blanket: design improvement and FEM studies (in session "P2")
P2.161 Tritium Removal system for the Experimental Pilot Plant for D-T separation located at Rm. Valcea (in session "P2")
P2.163 Conceptual design of the Enhanced Coolant Purification Systems for the European HCLL and HCPB Test Blanket Modules (in session "P2")
P2.164 ARC reactor: Activation analysis of the liquid blanket and structural materials for the vessel (in session "P2")
P2.165 On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour (in session "P2")
P2.166 Commissioning of Multi-Nozzle Vacuum Sieve Tray at the Tritium Laboratory Karlsruhe (in session "P2")
P2.167 Numerical study and experimental verification of protium permeation through Pd/Ag membranes for fusion applications (in session "P2")
P2.168 Synthesis of SiC films as tritium permeation barriers with high growth rate using a helicon wave plasma technique (in session "P2")
P2.169 Feasibility study for long-lived fission products transmutation using fusion reactors (in session "P2")
P2.170 Evolution of constrained beryllium pebble bed mock-ups neutron-irradiated up to 6000 appm helium production (in session "P2")
P2.171 On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behaviour (in session "P2")
P2.172 The production and molecular occurrence of radiotoxic Po-210 in liquid Pb-Li tritium breeding blankets (in session "P2")
P2.173 Fuel Retention Diagnostic Setup (FREDIS) for desorption of beryllium and tritium containing samples (in session "P2")
P2.174 Systems Engineering approach in support to the breeding blanket design (in session "P2")
P2.176 Deuterium permeation behavior through reduced activation ferritic steel F82H under DEMO reactor blanket condition (in session "P2")
P2.178 Iron-ion irradiation effects on microstructure and deuterium permeation in yttrium oxide coating fabricated by magnetron sputtering (in session "P2")
P2.179 Numerical investigation of mechanical and thermal characteristics of binary-sized pebble bed using discrete element method (in session "P2")
P2.180 Discrete element code to simulate the heat transfer inside ceramic breeder pebble beds (in session "P2")
P2.182 Scope of modification of the TRINITI site fuel cycle complex for the IGNITOR project tasks (in session "P2")
P2.184 Design of an industrial catalytic membrane reactor prototype for tritiated gaseous effluent treatment (in session "P2")
P2.185 Nuclear analysis of the HCLL “advanced-plus” breeding blanket with single module segment structure (in session "P2")
P2.186 DEMO Breeding Blanket Helium Cooled First Wall design investigation to cope high heat loads (in session "P2")
P2.187 Experimental investigation on HCLL-TBS In-box LOCA (in session "P2")
P2.189 The plan of continuous tritium recovery campaign by PbLi droplets in vacuum (in session "P2")
P2.190 Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors (in session "P2")
P2.191 Optimal operation and pump regeneration plan of fusion fuel cycle based on the state-task network representation (in session "P2")
P2.192 Design of Chinese Demo Blanket Concepts and R&D Progress of DFLL TBM (in session "P2")
P2.193 Synthesis densification and mechanical properties of nanometric tungsten for fusion applications (in session "P2")
P2.194 Comparative study of thermal and microstructural properties of tungsten for the application to PFM (in session "P2")
P2.195 Development of the Dual-beam ion irradiation facility for FUsion materials (DiFU) at RBI Zagreb (in session "P2")
P2.196 Corrosion resistance of alumina forming steel and ceramic materials in liquid tin (in session "P2")
P2.197 Spinel-nitride based radiation tolerant optical materials (in session "P2")
P2.198 Grain scale constitutive modeling and simulation for reduced activation ferritic/martensitic steel (in session "P2")
P2.199 Overview of the Current Status of IFMIF-DONES Secondary Heat Removal System Design (in session "P2")
P2.200 Irradiation of the copper-based high entropy alloys for nuclear fusion (in session "P2")
P2.202 Irradiation damage mechanism of tungsten studied by cold neutrons (in session "P2")
P2.203 Conceptual design of STUMM module for characterization of neutron and gamma radiation fields during commissioning phase of IFMIF DONES (in session "P2")
P2.204 Results of 16 MeV proton irradiation on tungsten for fusion relevant damage (in session "P2")
P2.205 IFMIF-DONES Systems Engineering Approach (in session "P2")
P2.206 Precipitation phenomena during corrosion testing in the forced-convection Pb-15.7Li loop PICOLO (in session "P2")
P2.207 Properties of boron carbide ceramics made by various methods for use in ITER (in session "P2")
P2.208 Microstructure and mechanical property mapping of CuCrZr with complex and non-uniform thermal history (in session "P2")
P2.209 Measurement of thermal conductivity of Li2TiO3 pebble bed by laser flash method (in session "P2")
P2.210 Neutron induced Primary knock on spectra and displacement damage on fusion reactor materials (W Fe Cr Cu& Al) at energies up to 14.1 MeV energy (in session "P2")
P2.211 Fatigue characterization and modeling of CLAM steel under multi-axial non-proportional cycle loading (in session "P2")
P2.212 Effects of specimen thickness on high-temperature tensile and creep properties of F82H reduced-activation ferritic/martensitic steel (in session "P2")
P2.213 Analysis of radionuclidic purity of medical isotope production with d-Li neutron in A-FNS (in session "P2")
P2.216 Effect of Hydrogen on Corrosion Properties of Reduced Activation Ferritic/Martensitic Steel F82H (in session "P2")
P2.218 Progress in the design development of EU DEMO Helium-Cooled Pebble Bed primary heat transfer system (in session "P2")
P2.219 Tritium and Dust Source Term Inventory Evaluation Issues in the European DEMO reactor concepts (in session "P2")
P2.221 Accident analysis with MELCOR-fusion code for DONES lithium loop and accelerator (in session "P2")
P2.222 Analysis and possible reduction of fusion plant construction costs (in session "P2")
P2.223 Validation and sensitivity of CFETR design in EU systems codes (in session "P2")
P2.224 Mesh based Variance Reduction Technique in Shielding Calculations of the Stellarator Power Reactor HELIAS (in session "P2")
P2.225 Assessment on radioactivity source term release and public impact for CFETR (in session "P2")
P2.229 Methodology of probabilistic risk assessment for tokamak-type fusion reactors (in session "P2")
P2.230 Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code (in session "P2")
P2.231 Experimental activities for in-box LOCA of WCLL BB in LIFUS5/Mod3 facility (in session "P2")
P2.232 Testing of some potential techniques for the DEMO radioactive waste management (in session "P2")
P2.233 First considerations on the Balance of Plant for a HELIAS power plant (in session "P2")
P2.234 Validation of SIMMER-III code for in-box LOCA of WCLL BB based on Test D1.1 of LIFUS5/Mod3 facility (in session "P2")
P2.235 Overview of the Methods developed for Fission Plants Safety relevant to the Safety of Fusion Facilities (in session "P2")
P2.236 Biomass gasification with high temperature heat and economic assessment of Fusion-Biomass Hybrid System (in session "P2")
P2.237 Experimental measurements of pressure temperature and dust velocities: comparisons with a multiphase numerical model (in session "P2")
P2.238 Experiment study of spectrum of air bubble flash lamp (in session "P2")
P3.001 Quasi-optical polarizer system for ECH/ECCD experiments in the QUEST spherical tokamak (in session "P3")
P3.002 ST40: engineering commissioning first results (in session "P3")
P3.003 Conceptual design of low aspect ratio superconducting tokamak with high magnetic field (T15-SC) (in session "P3")
P3.005 A new upper divertor with internal coils for ASDEX Upgrade - status of the project (in session "P3")
P3.006 Recent development and physical improvements of AFSI-ASCOT based synthetic neutron diagnostics at JET (in session "P3")
P3.007 Fusion device components Hot Helium Leak Test facilities main requirement and lessons learned from the WEST project (in session "P3")
P3.008 Magnetic configurations and electromagnetic analysis of the Italian DTT device (in session "P3")
P3.009 Fast scenario design for EAST alternative magnetic diverted discharge (in session "P3")
P3.010 Design and manufacturing of thermal shield for JT-60SA (in session "P3")
P3.011 Status scientific results and technical improvements of the NBH on TCV tokamak (in session "P3")
P3.012 Design of Integrated Bivalent Auxiliary System (SABI) supporting the MITICA cooling plant and cryogenic plant (in session "P3")
P3.013 Status of development and commissioning of the TCV EC-system upgrade (in session "P3")
P3.014 Pre-qualification of the ELM resilient long pulse WEST ICRF launchers in the TITAN testbed (in session "P3")
P3.15 Continuous and Cryogen-free Isotope Separation for DEMO (in session "P3")
P3.015 Numerical analyses and tests for optimized and enhanced heat transfer solutions in DEMO (in session "P3")
P3.016 A high power helicon antenna for the DIII-D tokamak and its electromagnetic aspects (in session "P3")
P3.017 Conceptual definition of an ICRF system for the Italian DTT (in session "P3")
P3.018 Design of the 105GHz electron cyclotron resonance heating system on J-TEXT (in session "P3")
P3.019 42GHz ECRH system on Aditya Upgrade (in session "P3")
P3.20 2Development of a novel irradiation chamber to assess the influence of magnetic fields on radiation damage in materials (in session "P3")
P3.020 A new tungsten wire calorimeter for the negative ion source testbed BATMAN-Upgrade (in session "P3")
P3.021 Modeling neutral beam transport in fusion experiments: Studying the effects of reionisation and deflection (in session "P3")
P3.022 Development of two directional beam steering ECH/CD launcher for JT-60SA (in session "P3")
P3.024 Anode power supply for the electron cyclotron resonacne heating system on J-TEXT tokamak (in session "P3")
P3.025 The heating systems capability of DTT (in session "P3")
P3.026 Achievements of the ELISE test facility in view of the ITER NBI (in session "P3")
P3.027 SPIDER Gas Injection and Vacuum System: from Design to Commissioning (in session "P3")
P3.028 Design of KSTAR ECH launcher for long pulse high performance Tokamak operation (in session "P3")
P3.029 Test of polarizers for the 105 GHz ECRH system on J-TEXT (in session "P3")
P3.030 Optimization of TE11/TE04 Mode Converters for the Cold Test of a 250 GHz CARM Source (in session "P3")
P3.031 DONES Central Instrumentation and Control Systems: general overview (in session "P3")
P3.032 Research on establishment methods of basic survey control network for HL-2M tokamak (in session "P3")
P3.033 Plasma equilibrium based on EC-driven current profile with toroidal rotation on QUEST (in session "P3")
P3.034 Disruption simulation for design of JT-60SA components. (in session "P3")
P3.035 Data model implementation in ITER data archiving system (in session "P3")
P3.036 NI p2p streaming powered multiple fpga real-time data processing system on J-TEXT tokamak diagnostics (in session "P3")
P3.038 Assessment of linear disruption predictors using JT-60U data (in session "P3")
P3.039 Designing CODAC System for Tokamaks Using Web Technology (in session "P3")
P3.040 Requirements management support for the ITER PCS in view of first plasma operations (in session "P3")
P3.042 Remote control of a high-speed pellet injector and data synching & sharing tools (in session "P3")
P3.043 Development of the KSTAR Alarm Management System (in session "P3")
P3.044 Sensitivity of fast ion losses to magnetic perturbations in the European DEMO (in session "P3")
P3.045 Simulation of magnetic control of the plasma shape on the DEMO tokamak (in session "P3")
P3.046 Towards an automatic filament detector with a Faster R-CNN on MAST-U (in session "P3")
P3.047 First Wall and Divertor Protection in JET-ILW: Assessment of Reliability after fifty Hours of Plasma Operation (in session "P3")
P3.048 Study of the methods to enhance infrared emissivity of Molybdenum surface (in session "P3")
P3.049 New data acquisition control software developments for the simultaneous control of ten intelligent overview video cameras at W7-X (in session "P3")
P3.050 Structural analysis of the ITER ex-vessel PPR components located in the Gallery (in session "P3")
P3.051 Measurement of neutron flux emitted from 14 MeV DT generator (in session "P3")
P3.052 UWAVS first mirror after long plasma cleaning: surface properties and material re-deposition issues (in session "P3")
P3.053 Design of inductive sensors and data acquisition system for magnetic diagnostic of the T-15MD tokamak (in session "P3")
P3.054 Real-time waveform classification in TJ-II Scattering Thomson diagnostic using ensemble methods (in session "P3")
P3.055 LIBS system on linear plasma device PSI-2 for in situ diagnostics of plasma-facing materials (in session "P3")
P3.056 Measurement of edge plasma parameters at W7-X using Alkali Beam Emission Spectroscopy (in session "P3")
P3.057 Geometrical effect in the measurement of the CXRS on EAST (in session "P3")
P3.058 Upgrade of the beam emission spectrometer on EAST (in session "P3")
P3.059 Laser transfer technique using wavefront correction and homogenizers for Thomson scattering diagnostics (in session "P3")
P3.060 Linux device driver for Radial Neutron Camera in view of ITER long pulses with variable data throughput (in session "P3")
P3.061 Divertor infrared thermography at COMPASS (in session "P3")
P3.062 High throughput spectrometer for plasma ion temperature fluctuations measurement on EAST (in session "P3")
P3.063 Design manufacturing and testing of a Long Focus Spectro-Telescope mockup for H-alpha diagnostic (in session "P3")
P3.065 A visible light high-speed imaging system and tomographic reconstruction of plasma emissivity in J-TEXT (in session "P3")
P3.066 Broad band ECE measuremenst in ECW heated plasmas (in session "P3")
P3.067 Overview of optical designs of the Port-Plug components for the ITER Equatorial Wide Angle Viewing System (WAVS) (in session "P3")
P3.068 The Radial Neutron Camera DAQ Prototype Performance Results (in session "P3")
P3.069 - Study for the microwave interferometer for high densities on COMPASS-U tokamak (in session "P3")
P3.070 Design of the new electromagnetic measurement system for RFX-mod upgrade (in session "P3")
P3.072 The JET Upgraded Toroidal Alfvén Eigenmode Active Diagnostic System (in session "P3")
P3.073 Prospects for the Hall sensors based steady-state magnetic diagnostic for future fusion power reactors (in session "P3")
P3.074 The ITER radial neutron camera in-port system: nuclear analyses in support of its design development (in session "P3")
P3.075 Design Updates of Magnet System for Korean Fusion Demonstration Reactor K-DEMO (in session "P3")
P3.077 ANALYSIS OF TORE SUPRA/WEST TOROIDAL FIELD COIL QUENCH AND THERMO-HYDRAULIC MODEL WITH SUPERMAGNET (in session "P3")
P3.078 Strain distribution in the Nb3Sn Rectangular Wind & React Conductor of the European DEMO project determined by inductive measurements (in session "P3")
P3.080 Development of Insulation Technology with Vacuum-pressure-impregnation (VPI) for ITER PF6 Double Pancakes (in session "P3")
P3.081 Development of the bronze processed Nb3Sn wires using various Cu-Sn-In ternary alloy matrices (in session "P3")
P3.082 Thermal-Hydraulic and Quench Analysis of the DEMO CS coil (in session "P3")
P3.083 Simulation and verification of air cooling system for MITICA High Voltage Deck installation in Padova (in session "P3")
P3.087 A quasi-3D thermal-hydraulic model for an HTS CroCo conductor (in session "P3")
P3.088 ITER TF coil OIS interface assembly tool (in session "P3")
P3.090 Manufacturing status of ITER PF6 double pancakes (in session "P3")
P3.091 Preliminary design of the island divertor coils on J-TEXT tokamak (in session "P3")
P3.092 Acceleration Grid Power Supply Conversion System of the MITICA Neutral Beam Injector: On Site Integration Activities and Tests (in session "P3")
P3.093 Detailed structural analysis of a graded TF coil winding pack for EU DEMO (in session "P3")
P3.094 Validation of the updated DTT TF coil conceptual design (in session "P3")
P3.095 Mechanical Analysis of the DTT central solenoida (in session "P3")
P3.096 The coil system preliminary design for a large-scale high-intensity magnetic field immunity test platform (in session "P3")
P3.097 THE CONCEPTUAL DESIGN OF FAST DISCHARGE RESISTOR SYSTEM FOR LARGE FUSION DEVICE (in session "P3")
P3.099 Design of the support structures of the DTT magnet system (in session "P3")
P3.100 Replacement of the NSTX-U Inner PF Coils (in session "P3")
P3.101 Welding technologies applied on casings for JT-60SA toroidal field magnet (in session "P3")
P3.102 Effect of initial microstructure on the retention and desorption of deuterium and helium from W exposed to plasma (in session "P3")
P3.103 Manufacturing and characterization of stainless steel / CuCrZr and stainless steel / Cu transition ring by explosive welding method (in session "P3")
P3.104 Tritium permeability in polycrystalline tungsten (in session "P3")
P3.105 Investigation of hot spots development on metallic PFCs in the JET-ILW (in session "P3")
P3.106 Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test (in session "P3")
P3.107 Heat Flux Uniformity Qualification for First Wall Panel Prototype (in session "P3")
P3.108 Manufacturing of the First Wall Panel-prototype for the ITER First Wall normal heat flux design (in session "P3")
P3.109 CFD simulation of the water cooling of the DEMO first wall under high heat flux exposure (in session "P3")
P3.110 Temperature dependence of hydrogen co-deposition with metals (in session "P3")
P3.111 Application of RANS CFD models for helium cooled first wall with fins for heat transfer enhancement (in session "P3")
P3.112 High heat-flux response of high-conductivity graphitic foam monoblocks (in session "P3")
P3.113 ENEA Ultrasound Test of Plasma Facing Units (in session "P3")
P3.114 Instrument for hydrogen isotopes irradiation and resident assessment (in session "P3")
P3.115 Tungsten sources and transport during Metal Rings Campaign in DIII-D* (in session "P3")
P3.116 Continuous laser illumination for in situ investigation of tungsten erosion under transient thermal loads (in session "P3")
P3.117 Permeation properties of deuterium in tungsten exposed to D-He mixture plasma (in session "P3")
P3.118 Effects of divertor leg length on detached plasma formation in linear plasma device (in session "P3")
P3.119 FABRICATION ROUTE OF THE ANSALDO-ENEA ITER INNER VERTICAL TARGET DIVERTOR FULL SCALE PROTOTYPE (in session "P3")
P3.121 Status and improvement of the high heat flux W monoblock type target with graded interlayer for application to DEMO divertor (in session "P3")
P3.122 Stability of Be-based coatings under annealing up to 1273 K (in session "P3")
P3.124 W2C reinforced tungsten: thermo-mechanical and microstructural properties (in session "P3")
P3.125 Life time estimation of ITER first wall mock ups by FEM simulations (in session "P3")
P3.127 On the alignment of the Scraper Elements at Wendelstein 7-X (in session "P3")
P3.128 Modeling study on divertor plasma by impurity seeding at different locations with SOLPS-ITER (in session "P3")
P3.129 Characterising the impact of castellations on the efficiency of induction heating during testing in the HIVE facility (in session "P3")
P3.130 Evaluation of feasibility and costs of alternative magnetic divertor configurations for DEMO (in session "P3")
P3.131 Direct numerical simulation of coolant water flow in plasma facing component (in session "P3")
P3.132 Fabrication and Factory Acceptance Test of ITER Sector Sub-assembly Tool (in session "P3")
P3.133 Neutronics analysis for ITER UP18 preliminary design (in session "P3")
P3.134 Validation of cyanide copper electrodeposited threaded insert for anti-seizing in tokamak vacuum vessel (in session "P3")
P3.135 Preliminary electromagnetic loads calculation for the divertor of K-DEMO (in session "P3")
P3.137 Initial Configuration Studies of the Upper Vertical Port of the European DEMO (in session "P3")
P3.138 Upper vertical neutron camera integrity report (in session "P3")
P3.139 Real-time volumetric rendering of radiation fields using 3D textures (in session "P3")
P3.140 Assessment on DEMO Water Cooled Lithium Lead alternative design configuration (in session "P3")
P3.141 F4E Load Transfer Procedure among Finite Element Models different in Topology or in Discretization (in session "P3")
P3.142 Maintenance Logistics for IFMIF-DONES (in session "P3")
P3.143 Design of inboard first wall for the initial operation phase of JT-60SA (in session "P3")
P3.144 Remote handling tools for hydraulic connection of divertor cassette in JT-60SA (in session "P3")
P3.145 Final Design and Structural Analysis of Sector Lifting Tool for ITER (in session "P3")
P3.146 Rescue and recovery studies for the DEMO blanket transporter (in session "P3")
P3.147 Thermo structural analysis of the in-vessel components of the ITER plasma position reflectometry system on the high field side (in session "P3")
P3.148 Towards an optimized maintenance of Tokamak devices tools and methods adopted for WEST (in session "P3")
P3.149 Design and manufacturing of the wendelstein 7-X cryo-vacuum pump (in session "P3")
P3.150 Design and Instrumentation of a Divertor Manipulator at Wendelstein 7-X (in session "P3")
P3.151 Thermal behavior of conceptual blankets in K-DEMO under decay heat induced by neutron irradiation (in session "P3")
P3.152 WEST regular in-vessel inspections with the Articulated Inspection Arm robot (in session "P3")
P3.153 Nuclear analysis for the Preliminary Design Review of the ITER Equatorial Port #12 (in session "P3")
P3.155 Assembly methodology and results for WEST platform PFCs positioning (in session "P3")
P3.156 Mechanical design of the hydraulic lift and rotation drive system for a DIII-D beamline (in session "P3")
P3.157 Fusion neutron generation and two-dimensional neutron measurement by imaging plate detector (in session "P3")
P3.158 Preliminary integration of reflectometry diagnostic inside the HCLL breeding blanket module for the EU DEMO (in session "P3")
P3.160 Investigation on cooling performance of WCLL BB First Wall for EU DEMO (in session "P3")
P3.161 Investigating Ceramic Breeder Pebble Beds Thermomechanics Evolution Using Novel Pressure Mapping Technology (in session "P3")
P3.162 Tritium transport model at breeder unit level for HCLL breeding blanket (in session "P3")
P3.163 Measurement and CFD simulation of flow mal-distribution in z-type manifolds of a fusion demo blanket (in session "P3")
P3.164 Progress of KSTAR pellet injection system (in session "P3")
P3.165 Estimation of thermophysicochemical properties in uranium-hydrogen (U-H) system (in session "P3")
P3.166 Investigation of influence factors for oxidation reaction of trace H2 and CH4. (in session "P3")
P3.167 Tritium separation via high-temperature proton-conducting ceramic pumps (in session "P3")
P3.168 Electromagnetic analysis of the water cooled breeder blanket for CFETR Phase II (in session "P3")
P3.169 Provisions for a cryogenic distillation process linked to a CECE process at ICSI Rm. Valcea (in session "P3")
P3.170 Enhanced tritium production in fusion-fission hybrids for the external consumption (in session "P3")
P3.171 Addressing the feasibility of inboard direct-line injection of high-speed pellets for core fuelling of DEMO (in session "P3")
P3.172 A set-up for studying synergistic isotope effects in the permeation processes of hydrogen isotopes through metals (in session "P3")
P3.173 V&V analyses of the GEANT4 Monte Carlo code with computational and experimental fusion neutronics benchmarks (in session "P3")
P3.174 New catalytic packing performance, theoretical and experimental characterization for LPCE process (in session "P3")
P3.175 A complete EM analysis of DEMO WCLL Breeding Blanket segments during VDE-up (in session "P3")
P3.176 MeV energy ions accelerators for simulation the neutrons damage in fusion reactor materials (in session "P3")
P3.177 Test facility for the measurement of tritium permeation through fusion power plant materials (in session "P3")
P3.178 Development of a SIMMER\RELAP5 coupling technique: a preliminary application to the LIFUS5/Mod3 test facility (in session "P3")
P3.179 Evaporation and condensation model for a cooling system of the LiPb cold trap device (in session "P3")
P3.180 Neutronics Analysis of fusion breeding blanket concept to reduce peak of nuclear heat distribution (in session "P3")
P3.181 Numerical analysis of heat transfer characteristics for pebbles bed with variable fluid flow and packing factor conditions (in session "P3")
P3.182 Effects of Pre-Dissociations of HTO and H2 on Tritium Recovery Rate of Purge Gas Flow in Tritium Breeding Blanket (in session "P3")
P3.183 Design prototyping and manufacturing of Johnston Couplings for the Cryopump for the MITICA test facility (in session "P3")
P3.184 Effects of Helium irradiation on hydrogen diffusion through erbium oxide coatings (in session "P3")
P3.186 Cryogenic distillation experimental stands for hydrogen isotopes separation (in session "P3")
P3.188 Numerical influence analysis of the packing structure for ceramic Li4SiO4 and Li2TiO3 pebble beds (in session "P3")
P3.189 High temperature hydrogen selective solid-state electrolyte sensor fabricated by slip casting (in session "P3")
P3.190 Lithium conducting ceramics for electrochemical sensors in molten metals (in session "P3")
P3.191 Method of determination and optimisation of the control parameters for an LPCE process (in session "P3")
P3.192 Comparative study of the neutronic performances of EU-WCLL and China-WCCB breeding blanket concepts (in session "P3")
P3.193 Study on the anisotropy in microstructure and tensile properties of the 12Cr ODS steel (in session "P3")
P3.194 Dielectric characterization of up to 0.1 dpa neutron irradiated insulating materials for fusion applications (in session "P3")
P3.195 Properties of low friction anti-seize coatings for fusion applications (in session "P3")
P3.196 Investigation of Fe-W interfaces in graded Fe/W composites for the first wall of DEMO (in session "P3")
P3.197 FNG Copper Benchmark Evaluation for the SINBAD Database (in session "P3")
P3.198 Quantitative analyses of interfacial strain by diffraction contrast TEM imaging in ODS steel (in session "P3")
P3.199 Development of W-monoblock divertor components with included thermal barrier interfaces (in session "P3")
P3.200 Preliminary Analysis on A Maintainable Test Cell Concept for IFMIF-DONES (in session "P3")
P3.203 Mechanical properties and microstructure of W/CuY and W/CuCrZr composites produced by hot isostatic pressing (in session "P3")
P3.204 Early results on deposition of W-Cr alloy by industrially available large scale technologies (in session "P3")
P3.205 Physical design of GDT-based fusion neutron source with 2-3 folds increase of Q (in session "P3")
P3.206 Characterization of ZAO® sintered getter material for use in fusion applications (in session "P3")
P3.207 Microstructural comparison of Oxide-Dispersion Strengthened Ferritic Steels produced by HIP and Spark Plasma Sintering (in session "P3")
P3.208 Creating high-resolution simulations of manufactured divertor components from X-ray and neutron tomography (in session "P3")
P3.209 Characterization and thermomechanical assessment of a SiC-sandwich material for Flow Channel Inserts in DCLL blankets (in session "P3")
P3.210 Using sodium as filling and heat-conducting material in the irradiation capsules of the IFMIF-DONES (in session "P3")
P3.211 Electrochemical techniques as innovative tools for fabricating divertor and blanket components in fusion technology (in session "P3")
P3.212 Microstructure of oxide dispersion strengthened copper fabricated by mechanical alloying and hot isostatic pressing (in session "P3")
P3.213 Design of the Main Building and Plant Systems of the IFMIF-DONES facility (in session "P3")
P3.214 Thermophysical and mechanical properties of W-Cu laminates produced by FAST joining (in session "P3")
P3.215 Er2O3 coatings of different structures and their corrosion resistance of type 316 stainless steel to liquid lithium (in session "P3")
P3.216 Commissioning of The Materials Detritiation Facility at Culham Science Centre (in session "P3")
P3.217 Fracture toughness characterization of Eurofer97 steels in EUROfusion using miniature multi-notch bend bar specimens (in session "P3")
P3.218 MIRA: a high fidelity system/design code for advanced fusion reactor system analysis (in session "P3")
P3.220 Modifications to the MELCOR-TMAP code to simultaneously treat multiple fusion coolants (in session "P3")
P3.221 Design and analysis of the improved configuration of the Power Conversion System for the EU-DEMO power plant (in session "P3")
P3.222 Impact of external costs on the penetration of fusion power plants in the future global electricity system (in session "P3")
P3.224 Project & Quality Management activities of ENEA's Fusion Program and use of the Primavera P6 software (in session "P3")
P3.225 RFP based Fusion-Fission Hybrid reactor model for nuclear applications. (in session "P3")
P3.226 How fusion power can contribute to a fully decarbonized European power mix after 2050. (in session "P3")
P3.227 Analysis of S-CO2 Brayton Power Cycles for Fusion power reactors (in session "P3")
P3.228 Studies on helium-3 separation at Cernavoda nuclear power plant (in session "P3")
P3.229 Implementation of the lead lithium eutectic properties in RELAP5/Mod.3.3 for nuclear fusion system applications (in session "P3")
P3.231 Neutronics study for DTT tokamak building (in session "P3")
P3.232 Radiation shielding requirements for the full power operation of the Linear IFMIF Prototype Accelerator (LIPAc) at Rokkasho (in session "P3")
P3.233 Generation of tritiated methane by reaction between tritium and methane on catalyst (in session "P3")
P3.234 Evaluation of the effect of impurities in concrete on shutdown dose and activation for fusion reactor facility (in session "P3")
P3.235 On scheduling methodology for large-scale R&D projects using TRL and critical chain and its application to fusion (in session "P3")
P3.238 Heating of dense plasma to > 10 keV by femtosecond laser pulse for ICF (in session "P3")
P3.0706 Qualification of ITER Poloidal-Field coil cryogenic components (in session "P3")
P3.804 Steady-state transverse heat transfer in a single channel CICC (in session "P3")
P4.001 Coupled seismic analyses of the ITER Tokamak Complex building and Tokamak machine (in session "P4")
P4.002 Characterization of the input beam to RFQ of the Linear IFMIF Prototype Accelerator (LIPAc) (in session "P4")
P4.003 The study on blowout system of EAST upper divertor (in session "P4")
P4.004 Characterization of JET neutron field for radiation studies in DD DT and TT plasmas (in session "P4")
P4.005 TRANSP-based optimization for tokamak scenario development (in session "P4")
P4.006 Design review for the Italian Divertor Tokamak Test facility (in session "P4")
P4.007 Neutral beam assisted plasma breakdown on tokamak COMPASS (in session "P4")
P4.008 Support structure of the COMPASS-U tokamak: validation by ANSYS modelling (in session "P4")
P4.009 Technological challenges for the design of the RFX-mod2 experiment (in session "P4")
P4.010 Increasing the integrated power input in W7-X (in session "P4")
P4.011 An innovative helicon plasma source for an alternative concept of DEMO negative ion beam injector (in session "P4")
P4.012 SPIDER BEAM SOURCE READY FOR OPERATION (in session "P4")
P4.013 Effect of a magnetic cusp configuration on ion species ratio in a NBI ion source (in session "P4")
P4.014 The 3.7GHz LHCD system on HL-2M tokamak (in session "P4")
P4.015 System of 28 GHz ECHCD with beam focusing launcher on the QUEST spherical tokamak (in session "P4")
P4.016 Development and improvement of KSTAR NBI2 ion sources (in session "P4")
P4.017 An overview of the in-vessel ICRF-diagnostics in the ASDEX-Upgrade tokamak (in session "P4")
P4.018 LHCD launcher study in KSTAR (in session "P4")
P4.019 Development of High-Power Pulse Neutral Beam Injection System for the Versatile Experiment Spherical Torus (in session "P4")
P4.020 Design of the small scale prototype accelerator for KSTAR negative-ion-based NBI (in session "P4")
P4.021 Commissioning of vacuum pumping system for the second KSTAR neutral beam injection system (in session "P4")
P4.022 Design of the Large Current Hydrogen Negative Ion Source by using Sheet Plasma (in session "P4")
P4.023 The fabrication and assembly of the beam source for the SPIDER experiment (in session "P4")
P4.024 Electrical integration of two 1MW/2s dual-frequency gyrotrons into the EC-system of the TCV tokamak (in session "P4")
P4.025 Approaching final design of the ITER EC H&CD Upper Launcher (in session "P4")
P4.027 The current status of the system additional heating of the complex of TSP TRINITI and objectives of modernization for the project of tokamak Ignitor (in session "P4")
P4.028 Development of cesium-free negative hydrogen/deuterium ion source by sheet plasma (in session "P4")
P4.029 Enhanced operation of the EU EC Test Facility (in session "P4")
P4.030 AUG flight simulator development (in session "P4")
P4.031 New features of the ECH control system in DIII-D and impact of power modulation on collector loading (in session "P4")
P4.032 Electromagnetic analyses of Single and Double Null configurations in DEMO device (in session "P4")
P4.033 Closed-loop simulation with Grad-Shafranov equilibrium evolution for plasma control system development (in session "P4")
P4.034 Modeling of ITER initiation scenarios using IMAS framework (in session "P4")
P4.035 Command and control system for STAR X-Ray source (in session "P4")
P4.036 Real Time Assessment of the Magnetic Diagnostic System in RFX-mod (in session "P4")
P4.037 Plasma Boundary Reconstruction in JET by Magnetic Measurements (in session "P4")
P4.039 Robust control of the current profile and plasma energy in EAST (in session "P4")
P4.040 Robust configuration of the JET real-time protection sequencer (in session "P4")
P4.041 Plasma shape control assessment for JT-60SA using the CREATE tools (in session "P4")
P4.042 Design of real-time feedback system for detachment control in COMPASS (in session "P4")
P4.043 ST40 Data and Control (in session "P4")
P4.044 Operational experience And evolution of the Real Time Protection Sequencer on JET (in session "P4")
P4.046 Runaway electrons diagnostics using segmented semiconductor detectors (in session "P4")
P4.047 Choice of the detectors for light impurities plasma studies at W7-X using C/O Monitor system (in session "P4")
P4.048 A neutron spectrometer based on diamond detector for D-D fusion neutron measurements on KSTAR (in session "P4")
P4.049 Effect of temperature on magnetic measurements in KSTAR tokamak (in session "P4")
P4.050 Polarimetric laser beam diffraction in tokamak plasma (in session "P4")
P4.052 Shutter systems for various diagnostics at the Wendelstein 7-X stellarator (in session "P4")
P4.054 On multistage development of ITER High Field Side Reflectometry diagnostic module design based on thermal stress numerical assessment (in session "P4")
P4.056 Integration of the TESPEL injection system at W7-X (in session "P4")
P4.057 Plasma cleaning of ITER diagnostic mirrors with coaxial λ/4 water-cooling line (in session "P4")
P4.059 Refurbishment of JET magnetic diagnostics (in session "P4")
P4.060 Heavy ion beam probe design and operation on the T-10 tokamak (in session "P4")
P4.061 Steady-state magnetic diagnostic for ITER and beyond (in session "P4")
P4.063 Functional and load testing of stepping-motor hexapod for positioning of H-alpha optical components in the ITER port interspace (in session "P4")
P4.064 Prototyping of stepping-motor hexapod for 6 DoF positioning of optical components in the ITER port interspace (in session "P4")
P4.065 The evaluation of server hardware for the fast online processing of X-ray impurities diagnostics in the WEST (in session "P4")
P4.066 Evaluation of the spectrum unfolding methodology for the neutron activation system of a fusion device (in session "P4")
P4.067 Modification of neutron emission spectrum by Alfven eigenmodes in a deuterium-tritium plasma (in session "P4")
P4.068 Thermography of the FTU toroidal limiter during disruptions (in session "P4")
P4.069 Structural Thermal Optical Performance analysis for full system optical performance assessment in complex environments (in session "P4")
P4.070 Performance evaluation of a hypothetical core density fluctuation measurement on the ITER diagnostic beam. (in session "P4")
P4.071 Thermal loads and cooling design for ITER in-port low field side reflectometer diagnostic system (in session "P4")
P4.072 Electromagnetic loads on ITER low field Side reflectometer in-vessel components (in session "P4")
P4.073 Doppler coherence imaging of impurity flows in the divertor of tokamaks and stellarators (in session "P4")
P4.075 Nuclear analysis of the collective thomson scattering system for iter (in session "P4")
P4.076 Extension of the high current power supplies of ASDEX Upgrade – The design of a new thyristor converter (in session "P4")
P4.077 Venturi flowmeters for the control of the ITER magnets (in session "P4")
P4.078 Implementation Details of an Upgrade to the EAST Poloidal Field Power Supply DAQ System (in session "P4")
P4.079 Research on Synchronization Technology of High-power Converters (in session "P4")
P4.080 A 15kA solid circuit breaker for the switch network unit of the EAST Tokamak (in session "P4")
P4.081 High voltage electrical system of 8.56 GHz CW klystron for electron cyclotron heating on QUEST spherical tokamak (in session "P4")
P4.082 Design and optimization of vacuum pressure impregnation mould for large scale superconducting coils (in session "P4")
P4.083 Concept design of high power quench protection circuit on China Fusion Engineering Test Reactor (in session "P4")
P4.084 Design a Suitable Test Scheme for Triggering Bypass Protection Test of ITER PF Converter Unit (in session "P4")
P4.085 Investigations on stable operational regions for SPIDER RF oscillators (in session "P4")
P4.086 HTS CroCo – Demonstration of long length fabrication (in session "P4")
P4.087 High voltage direct current power supplies for electron cyclotron resonance heating at ASDEX Upgrade (in session "P4")
P4.088 AC loss and stability analysis of EAST superconducting magnet in ELM triggering (in session "P4")
P4.089 Towards the completion of the Power Supply system for Resistive Wall Modes control in JT-60SA (in session "P4")
P4.090 Development of Supervisory Control System for Magnet Power Supplies in JT-60SA (in session "P4")
P4.091 MESS: a new Magnetic Energy Storage Scheme for improving the power handling in fusion experiments a conceptual study (in session "P4")
P4.092 The reactive power demand in DEMO: estimations and mitigation strategies (in session "P4")
P4.093 An arc electrical simulation method for superconducting magnet system in safety-related fault condition (in session "P4")
P4.094 Mechanical analysis of the European DEMO central solenoid pre-load structure and coils (in session "P4")
P4.095 Design and thermal coupling analysis of vpi mould for iter pf6 double pancake (in session "P4")
P4.096 Ultrasonic C-scanning technology application for low-temperature superconducting joint box material of ITER current lead (in session "P4")
P4.097 Design of the JT-60SA cryogenic pipe system (in session "P4")
P4.098 Tokamak coil operations by energy-conservation converters and distributed energy storage (in session "P4")
P4.099 Optimization of the cooling capacity of the cryo-magnetic system for EU DEMO at the pre-conceptual design phase (in session "P4")
P4.100 Analysis of the effect of a plasma disruption on the DTT Toroidal Field magnets (in session "P4")
P4.101 Conceptual design of the power supply systems for the Divertor Tokamak Test facility (in session "P4")
P4.102 Monitoring and Control of the Magnet System of JT-60SA (in session "P4")
P4.103 Experimental study on anti-fatigue performance for TIG Welding and EB welding of RAFM steel plate (in session "P4")
P4.105 Studies of advanced divertor concepts and engineering design issues for a DEMO reactor (in session "P4")
P4.106 Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution at operating condition (in session "P4")
P4.107 Additive manufacturing for realising a tailored tungsten-copper composite plasma-facing component heat sink (in session "P4")
P4.108 Development of 30 kW liquid metal handling system for plasma-facing experiments at DIFFER (in session "P4")
P4.109 Effect of Initial Condition on Seismic Analysis of the HCCR TBM-Set (in session "P4")
P4.110 Hydrogen and deuterium behavior on gas driven permeation through tungsten deposition layer on nickel plate (in session "P4")
P4.111 High heat flux qualification tests of HELCZA facility (in session "P4")
P4.112 Measures to overcome deep crack issues in the tungsten tiles of the ASDEX Upgrade divertor (in session "P4")
P4.114 Simulation study of evolution of helium bubbles in bulk W with vacancies (in session "P4")
P4.115 Depth profiles of deuterium in W coatings from the JET divertor measured by Glow Discharge Optical Emission Spectrometry (in session "P4")
P4.117 The influence of nitrogen on the deuterium retention within tungsten coatings for fusion applications (in session "P4")
P4.118 Reactor studies of hydrogen isotopes interaction with lithium CPS using dynamic sorption technique (in session "P4")
P4.119 Enhancements in the structural integrity assessment of plasma facing components (in session "P4")
P4.120 CFETR Integration Design Platform: Workflow for geometry design of divertor target (in session "P4")
P4.121 Testing of a high temperature radiatively cooled Li/Ta heat pipe in Magnum-PSI (in session "P4")
P4.123 DEMO First Wall misalignment study (in session "P4")
P4.124 High heat flux test results for a thermal break DEMO divertor target and subsequent design and manufacture development (in session "P4")
P4.126 Deuterium retention on the tungsten-coated divertor tiles of JET ITER-Like Wall in 2015-2016 campaign (in session "P4")
P4.127 Development of self-passivating W alloy / Eurofer brazed joints (in session "P4")
P4.128 Locally adapted heat transfer using variable height rib structures for Optimization of HCPB DEMO FW cooling channels (in session "P4")
P4.129 Investigation of beryllium damage under transient plasma heat loads in wide range of temperatures and heat loads (in session "P4")
P4.130 Characterisation of JET ILW divertor plasma facing surface materials by temperature-QMS analysis (in session "P4")
P4.132 Production of tungstenfibre reinforced tungsten composite by a novel continuous chemical vapour deposition process (in session "P4")
P4.133 Study of the ports effects on the CFETR radiation shielding (in session "P4")
P4.134 Numerical design approaval of port liner and bellows protection (in session "P4")
P4.135 A sophisticated remote maintenance method for the target assembly of Advanced Fusion Neutron Source (in session "P4")
P4.136 New methodology to improve execution efficiency and safety in remote maintenance tasks (in session "P4")
P4.137 Design and analysis of dual arm robot for the intelligence maintenance of CFETR (in session "P4")
P4.139 Development and Validation of Cryostat Finite Element Model with Unique FE Method (in session "P4")
P4.140 Profile Tolerances influence on Cryostat Base Section (in session "P4")
P4.141 Deformation Modeling and Compensation Control of Manipulators for DEMO (in session "P4")
P4.142 Heat Management for Water-Hydraulic Systems at ITER Remote Handling (in session "P4")
P4.143 Water quality and cleanliness effects on water hydraulic components in ITER remote handling maintenance systems (in session "P4")
P4.144 Thermal-hydraulic analysis for first wall and vacuum vessel thermal shield of Divertor Tokamak Test facility (in session "P1")
P4.145 Neutronics Studies for Horizontal Lower Port Option in DEMO (in session "P4")
P4.146 Preliminary source terms investigation for decontamination of fusion reactor in-vessel component maintenance process in hot cell (in session "P4")
P4.148 DEMO Breeding Blanket temperature evaluation before remote maintenance operation (in session "P4")
P4.149 Electromagnetic and structural analysis of COMPASS Upgrade vacuum vessel during disruptions (in session "P4")
P4.150 Parametric Modelling of Remote Maintenance Strategies and Concepts for EU DEMO (in session "P4")
P4.151 A simulation framework for dynamic analysis of flexible robotic mechanisms in DEMO remote maintenance (in session "P4")
P4.152 The DTT device: advances in conceptual design of first wall vessel and cryostat structures (in session "P4")
P4.154 Progress on reliability of remote maintenance concept for Japan’s fusion DEMO reactor (in session "P4")
P4.155 A design study of vacuum vessel and pumping system for COMPASS-U Tokamak (in session "P4")
P4.156 In-vessel viewing system prototype performance measurements and simulation of measurement quality across the ITER in-vessel components (in session "P4")
P4.157 Improvement of manufacturing jigs design for reduction of welding distortion in Vacuum Vessel PS1 through finite element analysis (in session "P4")
P4.158 Use of morphing techniques within weld distortion analysis to simulate the size customization of parts during assembly and welding of the Vacuum Vessel PS3 outer shell (in session "P4")
P4.159 Deep feature based detection and location of the damaged first wall for EAST Tokamak (in session "P4")
P4.160 Lithium-vaporization properties of Li8ZrO6 at medium temperature in 0.01% H2/He gas flow (in session "P4")
P4.161 Fabrication of thin-walled fusion blanket components like flow channel inserts by selective laser manufacturing (in session "P4")
P4.162 Evaluation of conservative and innovative manufacturing routes for gas cooled Test Blanket Module and Breeder Blanket First Walls (in session "P4")
P4.163 Investigation of Alumina Films Formed over Aluminized RAFM steels by Plasma Assisted Heat Treatments (in session "P4")
P4.164 Technical background on design of DS recombiner for fusion facility (in session "P4")
P4.165 Experimental study of liquid metal magnetohydrodynamic flows near gaps between flow channel inserts (in session "P4")
P4.166 Tritium breeding capability of water cooled ceramic breeder blanket with different container designs (in session "P4")
P4.167 Mechanical design and first experimental results of a new multi-tube Pd-Ag membrane reactor for hydrogen isotopes separation in solid blanket concept of nuclear fusion machines (in session "P4")
P4.168 Preliminary implementation of EU-DEMO primary heat transfer systems for HCPB breeding blanket option (in session "P4")
P4.169 Neutronic analyses of the ITER TBM Port Plug with Dummy TBMs (in session "P4")
P4.170 Numerical simulations of 3D magnetohydrodynamic flows for dual-coolant lead lithium blankets (in session "P4")
P4.171 EU DEMO WCLL BB breeding zone cooling system design: analysis and discussion (in session "P4")
P4.172 Fusion Technology Facilities & H3AT at UKAEA (in session "P4")
P4.173 The CIEMAT LiPb Loop for Permeation Experiments (in session "P4")
P4.174 Lithium isotope enrichment by electrodialysis using solid lithium electrolyte (in session "P4")
P4.175 Low pressure fusion exhaust gases separation (in session "P4")
P4.176 Thermal analysis of a cryogenic distillation column for H2 isotopes separation (in session "P4")
P4.177 Liquid-solid coupled interaction between thermal stress of FW and duct in CFETR blanket (in session "P4")
P4.178 Development of a computational procedure to simulate activation of coolant/breeding loops in DEMO reactors (in session "P4")
P4.179 Separation and recycle of Plasma Enhancement Gases using a CMS membrane (in session "P4")
P4.180 Radiation damage and helium accommodation in lithium metatitanate as a ceramic breeder material (in session "P4")
P4.181 Computer based architecture to control Water Detritiation Process (in session "P4")
P4.182 Simulating gas adsorption processes via kinetic modeling (in session "P4")
P4.183 Steam Generator mock-up design and testing suitable for Pb-Li technology demonstration and code assessment (in session "P4")
P4.184 Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL Breeding Blanket design (in session "P4")
P4.185 Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation (in session "P4")
P4.186 Evolution of tritium transfers in the lithium loop of IFMIF-DONES (in session "P4")
P4.187 Tritium operations at the Laboratory for Laser Energetics (in session "P4")
P4.188 Neutronics design analyses of helium cooled ceramic breeder blanket for CFETR phase 1 (in session "P4")
P4.189 Multifunctional Yttrium Oxide coatings for DEMO breeding blanket concepts employing Pb-16Li eutectic (in session "P4")
P4.190 Development of a water-cooled blanket concept with pressure tightness against in-box-LOCA for Japan’s DEMO (in session "P4")
P4.191 Development of PbLi facilities and experiments implement for fusion blanket technology (in session "P4")
P4.193 Microstructural evolution in neutron irradiated beryllium pebbles at DEMO relevant temperatures (in session "P4")
P4.194 Experimental verification of dosimetry reaction rates of Co Nb Au Bi with d-Li neutrons (in session "P4")
P4.195 Stress-strain characterization of abs polymer at cryogenic temperatures (in session "P4")
P4.196 Improved analysis on corrosion profile of liquid lithium in 304 stainless steel by LIBS (in session "P4")
P4.198 Iter sixth poloidal field coil insulation qualification (in session "P4")
P4.200 Evaluation of high heat removal efficiency using cooling water channel with rib structure (in session "P4")
P4.201 W-Cr and W-Ti alloys consolidated by field assisted sintering with and without carbon diffusion barrier (in session "P4")
P4.203 Analytical and numerical calculations for the diffusion welding specimens on a Gleeble 3800 thermomechanical simulator (in session "P4")
P4.204 Development of ductile phase toughened tungsten for fusion plasma facing applications (in session "P4")
P4.206 Neutron field study of p(24)+Be source reaction using the multi-foil activation technique (in session "P4")
P4.208 Mechanical alloying strategies for fabrication of new types of oxide dispersion strengthened low-activation one-phase high entropy alloys (in session "P4")
P4.209 The relationship between microstructure of ceramic coatings and γ-ray irradiation effect on deuterium permeation (in session "P4")
P4.210 Fatigue behaviour of prospective fusion oxide dispersion strengthened CoCrFeNiMn high entropy alloy (in session "P4")
P4.211 OXIDATION BEHAVIOUR OF TUNGSTEN WITH VANADIUM ADDITIONS (in session "P4")
P4.213 Ion irradiation in oxide nanoceramics: on the role of the irradiation spectrum at extreme damage levels (in session "P4")
P4.214 Transmission Kikuchi diffraction on carbon extraction replicas: a novel high statistics precipitate characterization pathway for Eurofer-97 steel. (in session "P4")
P4.215 Laser resistance of plasma-facing diagnostic components in ITER (in session "P4")
P4.216 A Plan of Purification System for Lithium Loop of Advanced Fusion Neutron Source (in session "P4")
P4.217 Fracture resistance study of tungsten wires as base material of fibre-reinforced plasma facing components (in session "P4")
P4.218 Neutronics Analyses of the Bio-shield and Liner of the IFMIF-DONES Test Cell (in session "P4")
P4.219 A revised and expanded liquid metal property library for MELCOR (in session "P4")
P4.220 Measurement of Neutron Spectrum using Activation Method in Deuterium Plasma Experiment at LHD (in session "P4")
P4.221 Experimental investigation of a Helium-cooled Breeding Blanket First Wall under LOFA conditions in view of code validation (in session "P4")
P4.223 Optimization of knowledge transfer in ITER (in session "P4")
P4.224 Verification of SuperMC with HCLL mock-up experiment (in session "P4")
P4.225 Development and Validation of Shutdown Dose Rate Calculation in SuperMC (in session "P4")
P4.226 The monitoring and determination of Beryllium contamination at HELCZA facility (in session "P4")
P4.227 Development and Application of Neutronics Design Software SuperMC for Fusion (in session "P4")
P4.228 Assessment of Serpent 2 application for fusion radiation transport analysis (in session "P4")
P4.229 An optimized code system for activation and shut-down dose rate calculations (in session "P4")
P4.230 JET work effort data collection for ITER operational radiation exposure optimization. (in session "P4")
P4.232 Neutron flux uncertainty propagation in R2S-based shutdown dose rate calculations (in session "P4")
P4.233 Benchmark of in-vessel Loss-Of-Coolant-Accident models for an EU DEMO helium-cooled blanket: GETTHEM vs. RELAP5-3D (in session "P4")
P4.234 Safety Important Classification of DEMO components (in session "P4")
P4.235 EU DEMO safety and balance of plant requirements. Issues and possible solutions (in session "P4")
P4.236 Cernavoda Tritium Removal Facility – tritium supplier for fusion facilities (in session "P4")
P.228 Chemistry and Corrosion Research and Development for Water Cooling Circuits of EU DEMO (in session "P2")
Paschen testing of ITER Central Solenoid qualification module (in session "P1")
Path planning and space occupation for remote maintenance operations of transportation in DEMO (in session "P1")
Picosecond laser-induced ablation for depth-resolved analysis of first wall components in fusion devices (in session "O1.C")
Plan and progress of the fusion neutron sources at KAERI for fusion and fission applications (in session "P1")
Plasma control for EAST long pulse non-inductive H-mode operation in a quasi-snowflake shape (in session "O1.A")
Plasma light detection in the SPIDER beam source (in session "P1")
Platinum suported on graphene - PTFE as catalysts for isotopic exchange in a detritiation plant. Manufacturing and physical and microstructural analysis (in session "P1")
Possibility study of the partial neutron calibration for neutron flux monitors in torus devices (in session "P1")
Post-Mortem Analysis of ITER CS Helium Inlets Fatigue Tested at Cryogenic Temperature (in session "P1")
Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI (in session "P1")
Practical Implementation within the Electron Cyclotron Upper Launcher of the French INB Order of 2012 (in session "P1")
Prebaking of T-15MD vacuum vessel (in session "P1")
Preliminary accident analysis of ex-vessel LOCA for the European DEMO HCPB blanket concept (in session "P1")
Preliminary investigation on W foams as protection strategy for advanced FW PFCs (in session "P1")
Preliminary RAMI assessment for ITER test blanket module ancillary systems (in session "P1")
Preliminary structural assessment of the HELIAS 5-B breeding blanket (in session "P1")
Present Progresses and Activities on the Chinese Fusion Engineering Test Reactor (in session "I5.1")
Pressure tests supporting the qualification of the ITER EC H&CD upper launcher diamond window (in session "P1")
Progress in Development of ITER Diagnostic Pressure Gauges and Status of Interfaces with ITER Components (in session "P1")
Progress in high heat flux testing of European DEMO (in session "P1")
Progress in the pre-conceptual CAD engineering of European DEMO divertor cassette (in session "P1")
Progress in the production of the W7-X divertor target modules (in session "P1")
Progress of the EU activities for the ITER Divertor Inner Vertical Target procurement (in session "P1")
Progress on an Ion Cyclotron Range of Frequency System for DEMO (in session "O2.A")
Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak (in session "P1")
Progress on thermo-hydraulic and thermo-mechanical performances of Helium-Cooled-Molten-Lead-Ceramic-Breeder as near-term alternative blanket for EU-DEMO (in session "P1")
Protection of window assemblies against ECRH and CTS stray radiation in ITER (in session "P1")
Purification of Pb-16Li breeder from corrosion products (in session "P1")
Radiolysis study of EU Li4SiO4 reference breeder material from the HICU experiment (in session "P1")
Reactivity and thermal stability of ternary Be-Zr-V beryllides (in session "P1")
Recent achievements of the Pd-Ag membrane technologies in tritium extraction system applications (in session "O2.C")
Recent experiments with the European 1MW, 170GHz industrial CW and short-pulse gyrotrons for ITER (in session "P1")
Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion Project (in session "O2.C")
Reconstructing JET using LiDAR-vision fusion (in session "O1.C")
Registering micro-indentation of neutron-irradiated low-activation steel at high temperatures (in session "P1")
Reliability Assessment of remote maintenance strategy for CFETR Divertor (in session "P1")
Repair processes of W7-X target modules (in session "P1")
Role of the Italian DTT in the Power Exhaust implementation strategy (in session "I2.3")
Safety and environmental studies for a European DEMO design concept (in session "O3.C")
Safety aspects on the road towards fusion energy (in session "I6.2")
Scaling analysis and design for the test model of water-cooled ceramic breeder blanket (in session "P1")
Seismic analyses of the Double Closure Plate Sub-Plate for the ITER Electron Cyclotron Upper Launcher during the Vacuum Vessel baking scenario (in session "P1")
Sensitivity of First Wall thermal-mechanical performance on cooling channel geometry and thermal conductivity (in session "P1")
Servo valve endurance test for Water-Hydraulic systems in ITER-relevant conditions (in session "P1")
SMITER: a field-line tracing environment for ITER (in session "P1")
SPIDER in the roadmap of the ITER Neutral Beams (in session "I4.1")
SPIDER Integrated Commissioning (in session "O2.A")
Standardized integration of ITER diagnostics equatorial port plugs (in session "O2.B")
Status European procurement for ITER (in session "I2.1")
Status of the EU DEMO breeding blanket manufacturing R&D activities (in session "O1.B")
Strategies toward the Realization of the Helical Fusion Reactor FFHR-c1 (in session "P1")
Structural integrity assessment of an ITER ECH&CD Upper Launcher mirror (LM1) (in session "P1")
Supplementary neutronics analysis of DEMO WCLL including activity and decay heat (in session "P1")
Supporting analysis of the ITER TBM Frame and Dummy TBM designs (in session "P1")
Surface oxidation effect on deuterium permeation in reduced activation ferritic steel F82H for DEMO application (in session "P1")
T-15MD tokamak plasma control platform architecture (in session "P1")
Technical proposals for the IGNITOR control, data access and communication system (in session "P1")
Temporary stagnation in the recrystallization of warm-rolled tungsten in the temperature range from 1150 °C to 1300 °C (in session "P1")
Testing of ceramic membranes for PEG separation and preliminary design of a membrane cascade (in session "P1")
The added value working under ISO 9001 in nuclear fusion technology R&D at ENEA (in session "P1")
The CNESM neutron imaging diagnostic for SPIDER beam source (in session "O2.A")
The Design of the DONES Lithium Target System (in session "P1")
The development of technology of Be/CuCrZr joining using induction brazing (in session "P1")
The helium turbo circulator – the heart of cooling systems (in session "P1")
THE HIGH VOLTAGE DECK 1 AND BUSHING FOR THE ITER NEUTRAL BEAM INJECTOR: INTEGRATED DESIGN AND INSTALLATION IN MITICA EXPERIMENT (in session "P1")
The ITER in vessel coils – design finalization and challenges (in session "P1")
The mega amp spherical tokamak real-time protection system (in session "O3.C")
The new attempts for the in-vessel pressure gauge in the KSTAR plasma (in session "P1")
The remote handling systems of ifmif-dones (in session "P1")
Thermal diffusivity of ceramic breeder beds (in session "P1")
Thermal Induced Electromotive Force Measurements On Twisted Pair Mineral Insulated Cables (in session "P1")
Thermal mixing enhancement of liquid metal film-flow by various obstacles under vertical magnetic field (in session "P1")
Thermal-mechanical analysis and design optimisations of the IFMIF-DONES HFTM (in session "P1")
Thermo-hydraulic analyses and fatigue verification of the Electrostatic Residual Ion Dump for the ITER HNB (in session "P1")
Thermo-Mechanical behaviour of ITER Blanket Modules interface between First Wall and Shield Block (in session "P1")
Thermomechanical simulation of flat tiles mock-ups under high heat flux (in session "O3.A")
Thermometric chains for ITER superconductive magnets (in session "P1")
Three-dimensional model of DEMO-FNS reactor for neutronics calculations and radiation shield problems (in session "P1")
Tokamak T-15MD - two years before the physical start--up (in session "P1")
Towards the EU fusion-oriented neutron source: the Preliminary Engineering Design of IFMIF-DONES (in session "I5.3")
Towards tritium measurements in W based on ps-LIBS diagnostics (in session "P1")
TRANSP-based closed-loop simulations of current profile optimal regulation in NSTX-Upgrade (in session "O3.C")
Tungsten coatings repair: an approach to increase the lifetime of plasma facing components (in session "P1")
Type tests of the ITER Switching Network Unit components and Protective Make Switches (in session "P1")
Type tests of the ITER Switching Network Unit components and Protective Make Switches (in session "P1")
Ultra high vacuum ZnSe window flange design for Phase Contrast Imaging diagnostics for the Wendelstein 7-X stellarator (in session "P1")
Uncertainty analysis of an SST-2 fusion reactor design (in session "P1")
Updated Conceptual Design of the DTT magnet system (in session "O3.B")
Updated design and integration of the ancillary circuits for the European Test Blanket Systems (in session "O2.C")
Updated design of the water cooled breeder blanket for CFETR (in session "O2.C")
Upgrade of Thomson scattering system on VEST (in session "P1")
VERDI detector benchmark experiment at the ENEA 14 MeV Frascati Neutron Generator (in session "O2.B")
Verification of hydraulic performance for the DEMO divertor target cooling (in session "P1")
W7-X: Technology progress of the experimental campaign with divertor plasmas (in session "I3.3")
WEST CODAC software quality management (in session "P1")
Work-flow process from simulation to operation for the Plasma Control System for the ITER First Plasma. (in session "P1")
X-ray induced defects in advanced lithium orthosilicate pebbles with additions of lithium metatitanate (in session "P1")
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