8 research outputs found

    Measuring fast ions in fusion plasmas with neutron diagnostics at JET

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    A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors

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    The objective of thermonuclear fusion consists of producing electricity from the coalescence of light nuclei in high temperature plasmas. The most promising route to fusion envisages the confinement of such plasmas with magnetic fields, whose most studied configuration is the tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one of the main potential showstoppers on the route to a commercial reactor. In this work we report how, deploying innovative analysis methods on thousands of JET experiments covering the isotopic compositions from hydrogen to full tritium and including the major D-T campaign, the nature of the various forms of collapse is investigated in all phases of the discharges. An original approach to proximity detection has been developed, which allows determining both the probability of and the time interval remaining before an incoming disruption, with adaptive, from scratch, real time compatible techniques. The results indicate that physics based prediction and control tools can be developed, to deploy realistic strategies of disruption avoidance and prevention, meeting the requirements of the next generation of devices.Confining plasma and managing disruptions in tokamak devices is a challenge. Here the authors demonstrate a method predicting and possibly preventing disruptions and macroscopic instabilities in tokamak plasma using data from JET

    Integrated modelling of H-mode pedestal and confinement in JET-ILW

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    Axisymmetric global Alfve虂n eigenmodes within the ellipticity-induced frequency gap in the Joint European Torus

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    Evidence of9Be + pnuclear reactions during 2蠅CHand hydrogen minority ICRH in JET-ILW hydrogen and deuterium plasmas

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    Light impurity transport in JET ILW L-mode plasmas

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    Effects of nitrogen seeding on core ion thermal transport in JET ILW L-mode plasmas

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    Overview of T and D鈥揟 results in JET with ITER-like wall

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    In 2021 JET exploited its unique capabilities to operate with T and D鈥揟 fuel with an ITER-like Be/W wall (JET-ILW). This second major JET D鈥揟 campaign (DTE2), after DTE1 in 1997, represented the culmination of a series of JET enhancements鈥攏ew fusion diagnostics, new T injection capabilities, refurbishment of the T plant, increased auxiliary heating, in-vessel calibration of 14 MeV neutron yield monitors鈥攁s well as significant advances in plasma theory and modelling in the fusion community. DTE2 was complemented by a sequence of isotope physics campaigns encompassing operation in pure tritium at high T-NBI power. Carefully conducted for safe operation with tritium, the new T and D鈥揟 experiments used 1 kg of T (vs 100 g in DTE1), yielding the most fusion reactor relevant D鈥揟 plasmas to date and expanding our understanding of isotopes and D鈥揟 mixture physics. Furthermore, since the JET T and DTE2 campaigns occurred almost 25 years after the last major D鈥揟 tokamak experiment, it was also a strategic goal of the European fusion programme to refresh operational experience of a nuclear tokamak to prepare staff for ITER operation. The key physics results of the JET T and DTE2 experiments, carried out within the EUROfusion JET1 work package, are reported in this paper. Progress in the technological exploitation of JET D鈥揟 operations, development and validation of nuclear codes, neutronic tools and techniques for ITER operations carried out by EUROfusion (started within the Horizon 2020 Framework Programme and continuing under the Horizon Europe FP) are reported in (Litaudon et al Nucl. Fusion accepted), while JET experience on T and D鈥揟 operations is presented in (King et al Nucl. Fusion submitted)
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