Results of thermal Strain and Conductor Elongation upon Heat Treatment for Nb3Sn Cable-in-Conduit Conductors

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Results of thermal Strain and Conductor Elongation upon Heat Treatment for Nb3Sn Cable-in-Conduit Conductors

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Plasma turbulence simulations in a diverted tokamak with applied resonant magnetic perturbations

Design and Development of a Diagnostic System for a Non-Intercepting Direct Measure of the SPIDER Ion Source Beamlet Current

Heat-transfer at the interface between a metal and a non-metal: influence of ultra-thin interlayers, interface chemistry and atomic order

Global 'zero particle flux-driven' gyrokinetic analysis of the density profile for a TCV plasma

Tests and Qualification of the European 1 MW, 170 GHz CW Gyrotron in an ITER relevant configuration at SPC

Thermal, electromagnetic and structural analysis of gas baffles for the TCV divertor upgrade

A self-consistent multi-component model of plasma turbulence and kinetic neutral dynamics for the simulation of the tokamak boundary

Thermal, electromagnetic and structural analysis of gas baffles for the TCV divertor upgrade

Overview of physics studies on ASDEX Upgrade

Enhanced confinement in diverted negative-triangularity L-mode plasmas in TCV

The power threshold of H-mode access in mixed hydrogen-tritium and pure tritium plasmas at JET with ITER-like wall

Electromechanical investigations and quench experiments on sub-size HTS cables for high field EU-DEMO Central Solenoid

Plasma exhaust and divertor studies in Japan and Europe broader approach, DEMO design activity

Physics of runaway electrons with shattered pellet injection at JET

Status Status of the final design of the EC UPP launcher

First operations with caesium of the negative ion source SPIDER

The effect of the secondary x-point on the scrape-off layer transport in the TCV snowflake minus divertor

Runaway dynamics in tokamak disruptions with current relaxation

Mitigation of divertor heat loads by strike point sweeping in high power JET discharges

Turbulent transport regimes in the tokamak boundary and operational limits