WP.TE in FSD is focusing on ITER, DEMO, and PEX with research topics ranging from alternative ELM regimes to divertor detachment physics. The meeting preparation includes discussing priorities like small ELMs and dust, while also addressing the expected availability and operation of devices such as

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The WPPWIE-ADC project within the EUROfusion Consortium is making significant strides in advancing divertor solutions for fusion reactors like DEMO. Key milestones include boundary code improvements, development of reduced models, and compatibility assessments with the DTT facility. The recent proje

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The project status for the VUV divertor spectrometer installation and commissioning is progressing well. The main components include collecting mirrors, toroidal mirrors, and gratings. The design is nearing completion with adjustments being made to the sustaining structure, mirrors, and periscope. T

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Study on the plasma-facing geometry design based on power shell geometry in the SOL TKT W-divertor development for the fusion reactor. The research involves fundamental differences in divertor baffle design, materials used, heat load requirements, interface connections, and key design concerns. The

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Divertor and main gas injection systems in OP2 have sophisticated feedback controllers ensuring precise gas flow control. Diagnostic signals availability includes interferometer data, CoDa station information, bolometer readings, and more for OP2.1 and OP2.2. Various sensors and instruments are in p

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Explore proposals on divertor plugging, effect of planar coil currents, Poincare maps, and main goal of loading PFCs for fusion reactors. The discussions aim to enhance plasma control strategies and optimize reactor performance.

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Experimentally investigate advanced divertors on NSTX to design an FNSF divertor, overcoming challenges of the standard divertor. Explore divertor performance through experimental studies and comparisons of different geometries. Detachment caused instability in the standard divertor is explained heu

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Explore the application of Collisional-Radiative Models (CRM) in EIRENE simulations for plasma detachment control in tokamaks. Learn about detached plasma divertor, main reactions in transport, vibrational states in molecular species, and more through a detailed study of particle species, reaction t

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