Tracer-Encapsulated Solid Pellet (TESPEL) injection system for Wendelstein 7-X-Reference-Cited by-同舟云学术

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Tracer-Encapsulated Solid Pellet (TESPEL) injection system for Wendelstein 7-X

Published:2018-10 Issue:10 Volume:89 Page:10K112
ISSN:0034-6748
Container-title:Review of Scientific Instruments
language:en
Short-container-title:Review of Scientific Instruments

Author:

Bussiahn R.¹^ORCID,Tamura N.²³,McCarthy K. J.⁴,Burhenn R.¹,Hayashi H.²,Laube R.¹,Klinger T.¹, ,

Affiliation:

1. Max-Planck-Institut für Plasmaphysik, Greifswald, Germany

2. National Institute for Fusion Science, National Institutes of Natural Sciences, Toki, Japan

3. SOKENDAI (The Graduate University of Advanced Studies), Toki, Japan

4. Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Madrid, Spain

Funder

National Institute for Fusion Science

H2020 Euratom

Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas

Publisher

AIP Publishing

Subject

Instrumentation

Link

http://aip.scitation.org/doi/pdf/10.1063/1.5038844

Reference15 articles.

1. Tracer-encapsulated solid pellet injection system

2. Confinement physics study in a small low aspect ratio helical device: CHS

3. Transport characteristics of tracer and intrinsic impurities depending on the density of LHD plasmas

4. Tracer-Encapsulated Solid Pellet (TESPEL) injection system for the TJ-II stellarator

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1. Impurity transport study based on measurement of visible wavelength high-n charge exchange transitions at W7-X;Nuclear Fusion;2024-07-11

2. Theoretical interpretation of W soft X-ray spectra collected by the pulse height analysis system on Wendelstein 7-X stellarator;Physics of Plasmas;2024-06-01

3. Performance of tungsten plasma facing components in the stellarator experiment W7-X: Recent results from the first OP2 campaign;Nuclear Materials and Energy;2023-12

4. Observation of impurity accumulation and its compatibility with high plasma performance in W7-X;Plasma Physics and Controlled Fusion;2023-08-29

5. Evaluation and validation of radial impurity density profiles from CXRS using neutral beam modelling in W7-X;Plasma Physics and Controlled Fusion;2023-06-06

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