Stellarator reactor-relevant fusion exhaust analysis, including diagnostic synthesis from experiments on W7-X
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Updated: Oct 31, 2026

Optimization, Test and Diagnostics of Miniaturized Hall Thrusters
Published on: February 16, 2019
C C Klepper1, S De Pascuale1, G Schlisio2
1Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA.
Abstract:
The (ITER-prototype) diagnostic residual gas analyzer (p-DRGA) was deployed in the W7-X OP2.3 experimental campaign, with emphasis on W7-X research applications, i.e., going beyond diagnostic capability demonstration focus of the previous campaigns. In addition to an initial validation of neutrals modeling in sub-divertor regions for helium exhaust applications and support of the associate ICRF-induced fast ion generation research program, the diagnostic system also provided early data relevant to an envisioned DRGA-enabled, stellarator reactor-relevant, fusion plasma burn control study, to be extended in OP2.4 and beyond. In this extended study concept, the fast ion generation would serve as proxy to the ICRF-enhanced DT burn approach used in JET-DTE2/DTE3, while the DRGA will provide the relevant species concentrations in real-time. Implicit in this concept is the correlation between core and sub-divertor concentrations, in ∼few sec equilibration time, which still needs validation for the case of stellarators.
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