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UKAEA-CCFE-PR(21)522021
Fusion has entered the engineering era. Moving from plasma science to experiments demonstrating the benefits of modified torus shapes and advanced divertor geometries, the ‘field’ has become an ‘industry’. Investors focus now on whether superconducting magnet joints are feasible in large tokamak designs and how to deliver net energy to g…
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UKAEA-CCFE-PR(21)472021
Visible emission from a broad range of tungsten charge states has complicated plasma ion temperature and toroidal rotation measurements on the JET tokamak since the installation of the ITER-like wall. A plethora of charge exchange emission lines from ions up to W 56+ and 21 suspected magnetic dipole emission lines have so far been observed. In p…
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UKAEA-CCFE-PR(21)462021
The fusion performance of ELMy H-mode DT plasmas with q95 = 3 and \\beta_N = 1.8 (also referred to as medium-\\beta_N baseline scenario in the rest of this paper) are predicted with the JINTRAC suite of codes and the QuaLiKiZ transport model. The predictions are based on the analysis of DT plasmas from the first DT campaign
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UKAEA-CCFE-PR(21)452021
Transport processes around the magnetic X-point of tokamaks, such as turbulence and mean-field drifts, are scarcely understood and difficult to investigate in experiments. In this paper, we explore the dynamics in a newly developed X-point scenario on the basic toroidal plasma device TORPEX and use it to validate plasma edge turbulence codes. In-si…
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UKAEA-CCFE-PR(21)442021
A model is presented for space charge neutralisation of positive ion beams. The model is used for the particular case of the beams used for magnetic based fusion applications. The beams consist, after a gas neutraliser, of ions and atoms at different energies. Account is taken of the co…
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UKAEA-CCFE-PR(21)432021
The chapter is devoted to materials used in controlled fusion facilities. Material solutions for magnetic confinement fusion devices and inertial confinement fusion facilities are described. Fusion materials have to preserve their performance often under extremely harsh conditions characterized by intensive particle fluxes, high levels of neutron i…
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UKAEA-CCFE-PR(21)422021
Tungsten and tungsten alloys are being considered as leading candidates for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for the design of magnetic and inertial fusion energy reactors are its high melting point, high thermal conductivity, low sputtering yield and low long-term di…
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UKAEA-CCFE-PR(21)412021
Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials of the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine the suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operatio…
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UKAEA-CCFE-PR(21)402021
The ability to detect undesired volumetric defects in reactor components could affect the safety and reliability of a fusion power plant and change the expected lifetime and performance of the reactor. This is even more true for critical reactor parts like plasma-facing components which have to withstand challenging in-vessel conditions due to a co…
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UKAEA-CCFE-PR(21)392021
A recently updated version of the MARS-F code [Y. Q. Liu et al. Phys. Plasmas 7, 3681 (2000); L. Li et al. Phys. Plasmas 25, 082512 (2018); G. L. Xia et al. Nucl. Fusion 59, 126035 (2019)] is utilized to numerically investigate the plasma screening effect on the applied resonant magnetic perturbation (RMP) field, assuming various equilibrium flo…
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