Isotope effects of the edge transport barrier of JET-ILW H-modes

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Future fusion power plants for clean energy production will need to operate with a mixture of different hydrogen isotopes, namely deuterium and tritium (D-T). The ITER experimental tokamak, currently being built in France, is an international fusion facility which will demonstrate burning plasma operation with D-T mixture. It is crucial to predict and optimise the fusion performance of ITER which requires deeper understanding of the effect of isotope mass on plasma confinement, transport and stability.The JET tokamak in the UK is in a phase of D-T experimental campaigns with both full tritium and deuterium-tritium operation. Together with the ITER-like combination of plasma facing components this phase addresses key aspects of operation with different hydrogen isotopes and will demonstrate ITER regimes in D-T. The project focuses on the analysis of JET-ILW edge plasma data in support of predictive models for the edge transport barrier. JET is in an excellent position for creating a high quality confinement and profile database suitable for studying core and edge contributions to the global confinement, to study the isotope scaling of the edge structure, to investigate the inter-ELM transport and the micro turbulence limiting the edge gradients.