Improvements on the Diagnostic Residual Gas Analyzer at Wendelstein 7-X

Georg Schlisio, Fabio A. Ravelli, C. Christopher Klepper, Jeffrey H. Harris, Theodore M. Biewer, Chris Marcus, Amit K. Kharwandikar, Dirk Naujoks, Thierry Kremeyer

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

Exhaust gas analysis provides key information on fusion processes, divertor operation, and wall state in fusion experiments and future reactors. The diagnostic residual gas analyzer (DRGA) concept has been developed for ITER with a focus on fast helium and hydrogen isotope detection. The first operation of the prototype DRGA (P-DRGA) at the stellarator Wendelstein 7-X showed potential for improvement in terms of magnetic sensor shielding, data acquisition automation, and potential new additions to the cluster of sensors on the P-DRGA. More recently, a Monte Carlo simulation of the flow of the mixed gas species effluent from the pressure-reducing orifice, down to about 8-m sampling tube and into the analysis region of the sensors, has been found to generally agree with previous calculations and measurements but revealed potential back-streaming effects for light gases, with impact on detection limits both for the prototype and for the ITER DRGA currently in design. For the upcoming campaign of the prototype, an enhanced soft iron shield will safeguard the gauges against magnetic stray field influence. The newly introduced shielding has been tested for its effect on magnetic stray fields and found to reduce the inside residual field by about two orders of magnitude.

Original languageEnglish
Pages (from-to)4120-4125
Number of pages6
JournalIEEE Transactions on Plasma Science
Volume50
Issue number11
DOIs
StatePublished - Nov 1 2022

Funding

The authors would like to thank laboratory support by A. von Stechow, N. Paschkowski, and C. Ahrens and would also like to thank the CVP image by M. Weißgerber. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No. 101052200—EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them.

FundersFunder number
A. von Stechow
European Commission101052200—EUROfusion

    Keywords

    • Electromagnetic shielding
    • fusion reactor design
    • vacuum technology

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