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Title: Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas

Abstract

In inboard-limited plasmas, foreseen to be used in future fusion reactor start-up and ramp down phases, the Scrape-Off Layer (SOL) exhibits two regions: the “near” and “far” SOL. The steep radial gradient of the parallel heat flux associated with the near SOL can result in excessive thermal loads onto the solid surfaces, damaging them and/or limiting the operational space of a fusion reactor. In this article, leveraging the results presented in the study by F. Nespoli et al. [Nucl. Fusion 57, 126029 (2017)], we propose a technique for the mitigation and suppression of the near SOL heat flux feature by impurity seeding. Here, the first successful experimental results from the TCV tokamak are presented and discussed.

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [2]; ORCiD logo [3]
  1. Ecole Polytechnique Fédérale de Lausanne (EPFL), Lausanne (Switzerland). Swiss Plasma Center (SPC)
  2. Ecole Polytechnique Fédérale de Lausanne (EPFL), Lausanne (Switzerland). Swiss Plasma Center (SPC); Univ. of California-San Diego, La Jolla, CA (United States)
  3. Univ. of California-San Diego, La Jolla, CA (United States)
Publication Date:
Research Org.:
Univ. of California, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
Contributing Org.:
TCV Team
OSTI Identifier:
1540175
Alternate Identifier(s):
OSTI ID: 1435485
Grant/Contract Number:  
SC0010529
Resource Type:
Accepted Manuscript
Journal Name:
Physics of Plasmas
Additional Journal Information:
Journal Volume: 25; Journal Issue: 5; Journal ID: ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; physics

Citation Formats

Nespoli, F., Labit, B., Furno, I., Theiler, C., Sheikh, U. A., Tsui, C. K., and Boedo, J. A. Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas. United States: N. p., 2018. Web. doi:10.1063/1.5023201.
Nespoli, F., Labit, B., Furno, I., Theiler, C., Sheikh, U. A., Tsui, C. K., & Boedo, J. A. Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas. United States. https://doi.org/10.1063/1.5023201
Nespoli, F., Labit, B., Furno, I., Theiler, C., Sheikh, U. A., Tsui, C. K., and Boedo, J. A. Tue . "Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas". United States. https://doi.org/10.1063/1.5023201. https://www.osti.gov/servlets/purl/1540175.
@article{osti_1540175,
title = {Impurity seeding for suppression of the near scrape-off layer heat flux feature in tokamak limited plasmas},
author = {Nespoli, F. and Labit, B. and Furno, I. and Theiler, C. and Sheikh, U. A. and Tsui, C. K. and Boedo, J. A.},
abstractNote = {In inboard-limited plasmas, foreseen to be used in future fusion reactor start-up and ramp down phases, the Scrape-Off Layer (SOL) exhibits two regions: the “near” and “far” SOL. The steep radial gradient of the parallel heat flux associated with the near SOL can result in excessive thermal loads onto the solid surfaces, damaging them and/or limiting the operational space of a fusion reactor. In this article, leveraging the results presented in the study by F. Nespoli et al. [Nucl. Fusion 57, 126029 (2017)], we propose a technique for the mitigation and suppression of the near SOL heat flux feature by impurity seeding. Here, the first successful experimental results from the TCV tokamak are presented and discussed.},
doi = {10.1063/1.5023201},
journal = {Physics of Plasmas},
number = 5,
volume = 25,
place = {United States},
year = {Tue May 01 00:00:00 EDT 2018},
month = {Tue May 01 00:00:00 EDT 2018}
}

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Cited by: 6 works
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Works referenced in this record:

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Works referencing / citing this record:

Numerical estimation of the oxygen impurity transport in the Aditya tokamak
journal, February 2020

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Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond
journal, August 2019