Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2

Hathiramani, D.; Ali, A.; Anda, G.; Barbui, T.; Biedermann, C.; Charl, A.; Chauvin, D.; Czymek, G.; Dhard, C. P.; Drewelow, P.; Dudek, A.; Effenberg, F.; Ehrke, G.; Endler, M.; Ennis, D. A.; Fellinger, J.; Ford, O.; Freundt, S.; Gradic, D.; Grosser, K.; Harris, J.; Hölbe, H.; Jakubowski, M. W.; Knaup, M.; Kocsis, G.; König, R.; Krause, M.; Kremeyer, T.; Kornejew, P.; Krychowiak, M.; Lambertz, H. T.; Jenzsch, H.; Mayer, M.; Mohr, S.; Neubauer, O.; Otte, M.; Perseo, V.; Pilopp, D.; Rudischhauser, L.; Schmitz, O.; Schweer, B.; Schülke, M.; Stephey, L.; Szepesi, T.; Terra, A.; Toth, M.; Wenzel, U.; Wurden, G. A.; Zoletnik, S.; Pedersen, T. Sunn

doi:10.1016/j.fusengdes.2018.02.013

Title: Upgrades of edge, divertor and scrape-off layer diagnostics of W7-X for OP1.2

Journal Article · Wed Feb 07 00:00:00 EST 2018 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2018.02.013· OSTI ID:1435175

Hathiramani, D.; Ali, A.; Anda, G.; Barbui, T.; Biedermann, C.; Charl, A.; Chauvin, D.; Czymek, G.; Dhard, C. P.; Drewelow, P.; Dudek, A.; Effenberg, F.; Ehrke, G.; Endler, M.; Ennis, D. A.; Fellinger, J.; Ford, O.; Freundt, S.; Gradic, D.; Grosser, K. more »

In this work, Wendelstein 7-X (W7-X) is the world’s largest superconducting nuclear fusion experiment of the optimized stellarator type. In the first Operation Phase (OP1.1) helium and hydrogen plasmas were studied in limiter configuration. The heating energy was limited to 4 MJ and the main purpose of that campaign was the integral commissioning of the machine and diagnostics, which was achieved very successfully. Already from the beginning a comprehensive set of diagnostics was available to study the plasma. On the path towards high-power, high-performance plasmas, W7-X will be stepwise upgraded from an inertially cooled (OP1.2, limited to 80 MJ) to an actively cooled island divertor (OP2, 10 MW steady-state plasma operation). The machine is prepared for OP1.2 with 10 inertially cooled divertor units, and the experimental campaign has started recently.The paper describes a subset of diagnostics which will be available for OP1.2 to study the plasma edge, divertor and scrape-off layer physics including those already available for OP1.1, plus modifications, upgrades and new systems. In conclusion, the focus of this summary will be on technical and engineering aspects, like feasibility and assembly but also on reliability, thermal loads and shielding against magnetic fields.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Contributing Organization:: the W7-X Team

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1435175

Journal Information:: Fusion Engineering and Design, Vol. 136, Issue A; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 4 works

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Cited By (2)

First demonstration of radiative power exhaust with impurity seeding in the island divertor at Wendelstein 7-X Effenberg, F.; Brezinsek, S.; Feng, Y. Nuclear Fusion, Vol. 59, Issue 10 https://doi.org/10.1088/1741-4326/ab32c4	journal	August 2019
Infrared imaging systems for wall protection in the W7-X stellarator (invited) Jakubowski, Marcin; Drewelow, Peter; Fellinger, Joris Review of Scientific Instruments, Vol. 89, Issue 10 https://doi.org/10.1063/1.5038634	journal	October 2018

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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