ITER LHCD plans and design

Ph. Bibet; B. Beaumont; J.H. Belo; J.P.S. Bizarro; L. Delpech; A. Ekedahl; G. Granucci; F. Kazarian; S. Kuzikov; Xavier Litaudon; J. Mailloux; F. Mirizzi; V. Pericoli; M. Prou; Karin Rantamäki; A.A. Tuccillo

doi:10.1109/FUSION.2005.252946

ITER LHCD plans and design

Ph. Bibet
, B. Beaumont
, J.H. Belo
, J.P.S. Bizarro
, L. Delpech
, A. Ekedahl
, G. Granucci
, F. Kazarian
, S. Kuzikov
, Xavier Litaudon
, J. Mailloux
, F. Mirizzi
, V. Pericoli
, M. Prou
, Karin Rantamäki
, A.A. Tuccillo

VTT Technical Research Centre of Finland

CEA Cadarache
Universidade de Lisboa
Institute of Plasma Physics “Pietro Caldirola” (CNR-IFP)
Russian Academy of Sciences: Institute of Applied Physics
Culham Science Centre
Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

5 Citations (Scopus)

Abstract

LH waves experimentally exhibit the highest Current Drive efficiency at low plasma temperature, therefore they are the most suitable candidates for controlling the current profile in the off axis part of ITER Steady State plasmas. For this purpose, a 5 GHz, 20 MW CW LH system has been designed, that relies on a generator made of 24 klystrons, 1 MW each, 60 metres long circular oversized transmission lines, and one antenna, based on the Passive Active Multifunction (PAM) concept High reliability of the launcher is achieved, by limiting the power density to 33 MW/m2. Together with the overall system description, the present results achieved toward ITER are presented The different ongoing projects are listed. The outstanding problems are depicted.

Original language	English
Title of host publication	21st IEEE/NPSS Symposium on Fusion Engineering
Publisher	IEEE Institute of Electrical and Electronic Engineers
ISBN (Print)	1-4244-0149-6
DOIs	https://doi.org/10.1109/FUSION.2005.252946
Publication status	Published - 2006
MoE publication type	A4 Article in a conference publication
Event	21st IEEE/NPSS Symposium on Fusion Engineering - Knoxville, United States Duration: 26 Sept 2005 → 29 Sept 2005

Conference

Conference	21st IEEE/NPSS Symposium on Fusion Engineering
Country/Territory	United States
City	Knoxville
Period	26/09/05 → 29/09/05

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

ITER
plasma
fusion energy
fusion reactors
Tokamak
antennas in plasma
fusion reactor design
plasma hybrid waves
plasma temperature
plasma transport processes
transmission lines
LH waves
LHCD design
antennas
current drive efficiency
low plasma temperature
power density

Access to Document

10.1109/FUSION.2005.252946

Cite this

Bibet, P., Beaumont, B., Belo, J. H., Bizarro, J. P. S., Delpech, L., Ekedahl, A., Granucci, G., Kazarian, F., Kuzikov, S., Litaudon, X., Mailloux, J., Mirizzi, F., Pericoli, V., Prou, M., Rantamäki, K., & Tuccillo, A. A. (2006). ITER LHCD plans and design. In 21st IEEE/NPSS Symposium on Fusion Engineering Article 4018980 IEEE Institute of Electrical and Electronic Engineers. https://doi.org/10.1109/FUSION.2005.252946

@inproceedings{d16a473619544bbca23e7f04ca276879,

title = "ITER LHCD plans and design",

abstract = "LH waves experimentally exhibit the highest Current Drive efficiency at low plasma temperature, therefore they are the most suitable candidates for controlling the current profile in the off axis part of ITER Steady State plasmas. For this purpose, a 5 GHz, 20 MW CW LH system has been designed, that relies on a generator made of 24 klystrons, 1 MW each, 60 metres long circular oversized transmission lines, and one antenna, based on the Passive Active Multifunction (PAM) concept High reliability of the launcher is achieved, by limiting the power density to 33 MW/m2. Together with the overall system description, the present results achieved toward ITER are presented The different ongoing projects are listed. The outstanding problems are depicted.",

keywords = "ITER, plasma, fusion energy, fusion reactors, Tokamak, antennas in plasma, fusion reactor design, plasma hybrid waves, plasma temperature, plasma transport processes, transmission lines, LH waves, LHCD design, antennas, current drive efficiency, low plasma temperature, power density",

author = "Ph. Bibet and B. Beaumont and J.H. Belo and J.P.S. Bizarro and L. Delpech and A. Ekedahl and G. Granucci and F. Kazarian and S. Kuzikov and Xavier Litaudon and J. Mailloux and F. Mirizzi and V. Pericoli and M. Prou and Karin Rantam{\"a}ki and A.A. Tuccillo",

year = "2006",

doi = "10.1109/FUSION.2005.252946",

language = "English",

isbn = "1-4244-0149-6",

booktitle = "21st IEEE/NPSS Symposium on Fusion Engineering",

publisher = "IEEE Institute of Electrical and Electronic Engineers",

address = "United States",

note = "21st IEEE/NPSS Symposium on Fusion Engineering ; Conference date: 26-09-2005 Through 29-09-2005",

}

Bibet, P, Beaumont, B, Belo, JH, Bizarro, JPS, Delpech, L, Ekedahl, A, Granucci, G, Kazarian, F, Kuzikov, S, Litaudon, X, Mailloux, J, Mirizzi, F, Pericoli, V, Prou, M, Rantamäki, K & Tuccillo, AA 2006, ITER LHCD plans and design. in 21st IEEE/NPSS Symposium on Fusion Engineering., 4018980, IEEE Institute of Electrical and Electronic Engineers, 21st IEEE/NPSS Symposium on Fusion Engineering, Knoxville, Tennessee, United States, 26/09/05. https://doi.org/10.1109/FUSION.2005.252946

TY - GEN

T1 - ITER LHCD plans and design

AU - Bibet, Ph.

AU - Beaumont, B.

AU - Belo, J.H.

AU - Bizarro, J.P.S.

AU - Delpech, L.

AU - Ekedahl, A.

AU - Granucci, G.

AU - Kazarian, F.

AU - Kuzikov, S.

AU - Litaudon, Xavier

AU - Mailloux, J.

AU - Mirizzi, F.

AU - Pericoli, V.

AU - Prou, M.

AU - Rantamäki, Karin

AU - Tuccillo, A.A.

PY - 2006

Y1 - 2006

N2 - LH waves experimentally exhibit the highest Current Drive efficiency at low plasma temperature, therefore they are the most suitable candidates for controlling the current profile in the off axis part of ITER Steady State plasmas. For this purpose, a 5 GHz, 20 MW CW LH system has been designed, that relies on a generator made of 24 klystrons, 1 MW each, 60 metres long circular oversized transmission lines, and one antenna, based on the Passive Active Multifunction (PAM) concept High reliability of the launcher is achieved, by limiting the power density to 33 MW/m2. Together with the overall system description, the present results achieved toward ITER are presented The different ongoing projects are listed. The outstanding problems are depicted.

AB - LH waves experimentally exhibit the highest Current Drive efficiency at low plasma temperature, therefore they are the most suitable candidates for controlling the current profile in the off axis part of ITER Steady State plasmas. For this purpose, a 5 GHz, 20 MW CW LH system has been designed, that relies on a generator made of 24 klystrons, 1 MW each, 60 metres long circular oversized transmission lines, and one antenna, based on the Passive Active Multifunction (PAM) concept High reliability of the launcher is achieved, by limiting the power density to 33 MW/m2. Together with the overall system description, the present results achieved toward ITER are presented The different ongoing projects are listed. The outstanding problems are depicted.

KW - ITER

KW - plasma

KW - fusion energy

KW - fusion reactors

KW - Tokamak

KW - antennas in plasma

KW - fusion reactor design

KW - plasma hybrid waves

KW - plasma temperature

KW - plasma transport processes

KW - transmission lines

KW - LH waves

KW - LHCD design

KW - antennas

KW - current drive efficiency

KW - low plasma temperature

KW - power density

U2 - 10.1109/FUSION.2005.252946

DO - 10.1109/FUSION.2005.252946

M3 - Conference article in proceedings

SN - 1-4244-0149-6

BT - 21st IEEE/NPSS Symposium on Fusion Engineering

PB - IEEE Institute of Electrical and Electronic Engineers

T2 - 21st IEEE/NPSS Symposium on Fusion Engineering

Y2 - 26 September 2005 through 29 September 2005

ER -

ITER LHCD plans and design

Abstract

Conference

UN SDGs

Keywords

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