Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database

X. Litaudon; E. Barbato; A. Bécoulet; E.J. Doyle; T. Fujita; P. Gohil; F. Imbeaux; O. Sauter; G. Sips; J. Connor; E.J. Doyle; Yu Esipchuk; T. Fujita; T. Fukuda; P. Gohil; J. Kinsey; N. Kirneva; S. Lebedev; X. Litaudon; V. Mukhovatov; J. Rice; E. Synakowski; K. Toi; B. Unterberg; V. Vershkov; M. Wakatani; T. Aniel; Yu F. Baranov; E. Barbato; A. Bécoulet; R. Behn; C. Bourdelle; G. Bracco; R.V. Budny; P. Buratti; E.J. Doyle; Yu Esipchuk; B. Esposito; S. Ide; A.R. Field; T. Fujita; T. Fukuda; P. Gohil; C. Gormezano; C. Greenfield; M. Greenwald; T.S. Hahm; G.T. Hoang; J. Hobirk; D. Hogeweij; S. Ide; A. Isayama; F. Imbeaux; E. Joffrin; Y. Kamada; J. Kinsey; N. Kirneva; X. Litaudon; T.C. Luce; M. Murakami; V. Parail; Y-K.M. Peng; F. Ryter; Y. Sakamoto; H. Shirai; G. Sips; T. Suzuki; E. Synakowski; H. Takenaga; T. Takizuka; Tuomas Tala; M.R. Wade; J. Weiland

doi:10.1088/0741-3335/46/5A/002

Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database

X. Litaudon^*
, E. Barbato
, A. Bécoulet
, E.J. Doyle
, T. Fujita
, P. Gohil
, F. Imbeaux
, O. Sauter
, G. Sips
, J. Connor
, E.J. Doyle
, Yu Esipchuk
, T. Fujita
, T. Fukuda
, P. Gohil
, J. Kinsey
, N. Kirneva
, S. Lebedev
, X. Litaudon
, V. Mukhovatov

J. Rice, E. Synakowski, K. Toi, B. Unterberg, V. Vershkov, M. Wakatani, T. Aniel, Yu F. Baranov, E. Barbato, A. Bécoulet, R. Behn, C. Bourdelle, G. Bracco, R.V. Budny, P. Buratti, E.J. Doyle, Yu Esipchuk, B. Esposito, S. Ide, A.R. Field, T. Fujita, T. Fukuda, P. Gohil, C. Gormezano, C. Greenfield, M. Greenwald, T.S. Hahm, G.T. Hoang, J. Hobirk, D. Hogeweij, S. Ide, A. Isayama, F. Imbeaux, E. Joffrin, Y. Kamada, J. Kinsey, N. Kirneva, X. Litaudon, T.C. Luce, M. Murakami, V. Parail, Y-K.M. Peng, F. Ryter, Y. Sakamoto, H. Shirai, G. Sips, T. Suzuki, E. Synakowski, H. Takenaga, T. Takizuka, Tuomas Tala, M.R. Wade, J. Weiland

^*Corresponding author for this work

BA4511 Fusion energy

Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)
University of California Los Angeles (UCLA)
Japan Atomic Energy Agency
General Atomics
Ecole Polytechnique Fédérale de Lausanne (EPFL)
Max-Planck-Institut für Plasmaphysik (IPP)
Culham Science Centre
Petersburg Nuclear Physics Institute
Osaka University
Lehigh University
Ioffe Institute
ITER Japan
MIT Massachusetts Institute of Technology
Princeton Plasma Physics Laboratory (PPPL)
National Institutes of Natural Sciences - National Institute for Fusion Science
Forschungszentrum Jülich GmbH (FZJ)
Kyoto University
Dutch Research Council
Oak Ridge National Laboratory (ORNL)
Chalmers University of Technology
KTH Royal Institute of Technology
CEA Cadarache

Research output: Contribution to journal › Article › Scientific › peer-review

37 Citations (Scopus)

Abstract

Advanced tokamak regimes obtained in ASDEX Upgrade, DIII-D, FT-U, JET, JT-60U, TCV and Tore Supra experiments are assessed both in terms of their fusion performance and capability for ultimately reaching steady-state using data from the international internal transport barrier database. These advanced modes of tokamak operation are characterized by an improved core confinement and a modified current profile compared to the relaxed Ohmically driven one. The present results obtained in these experiments are studied in view of their prospect for achieving either long pulses ('hybrid' scenario with inductive and non-inductive current drive) or ultimately steady-state purely non-inductive current drive operation in next step devices such as ITER. A new operational diagram for advanced tokamak operation is proposed where the figure of merit characterizing the fusion performances and confinement, H × β_N / q ²₉₅, is drawn versus the fraction of the plasma current driven by the bootstrap effect. In this diagram, present day advanced tokamak regimes have now reached an operational domain that is required in the non-inductive ITER current drive operation with typically 50% of the plasma current driven by the bootstrap effect (Green et al 2003 Plasma Phys. Control. Fusion 45 587). In addition, the existence domain of the advanced mode regimes is also mapped in terms of dimensionless plasmas physics quantities such as normalized Larmor radius, normalized collisionality, Mach number and ratio of ion to electron temperature. The gap between present day and future advanced tokamak experiments is quantitatively assessed in terms of these dimensionless parameters.

Original language	English
Pages (from-to)	A19-A34
Journal	Plasma Physics and Controlled Fusion
Volume	46
Issue number	5A
DOIs	https://doi.org/10.1088/0741-3335/46/5A/002
Publication status	Published - 2004
MoE publication type	A1 Journal article-refereed

UN SDGs

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

SDG 7 Affordable and Clean Energy

Keywords

JET
plasma
fusion energy
fusion reactors
tokamak
internal transport barriers
ITER

Access to Document

10.1088/0741-3335/46/5A/002

Cite this

Litaudon, X., Barbato, E., Bécoulet, A., Doyle, E. J., Fujita, T., Gohil, P., Imbeaux, F., Sauter, O., Sips, G., Connor, J., Doyle, E. J., Esipchuk, Y., Fujita, T., Fukuda, T., Gohil, P., Kinsey, J., Kirneva, N., Lebedev, S., Litaudon, X., ... Weiland, J. (2004). Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database. Plasma Physics and Controlled Fusion, 46(5A), A19-A34. https://doi.org/10.1088/0741-3335/46/5A/002

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title = "Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database",

abstract = "Advanced tokamak regimes obtained in ASDEX Upgrade, DIII-D, FT-U, JET, JT-60U, TCV and Tore Supra experiments are assessed both in terms of their fusion performance and capability for ultimately reaching steady-state using data from the international internal transport barrier database. These advanced modes of tokamak operation are characterized by an improved core confinement and a modified current profile compared to the relaxed Ohmically driven one. The present results obtained in these experiments are studied in view of their prospect for achieving either long pulses ('hybrid' scenario with inductive and non-inductive current drive) or ultimately steady-state purely non-inductive current drive operation in next step devices such as ITER. A new operational diagram for advanced tokamak operation is proposed where the figure of merit characterizing the fusion performances and confinement, H × βN / q 295, is drawn versus the fraction of the plasma current driven by the bootstrap effect. In this diagram, present day advanced tokamak regimes have now reached an operational domain that is required in the non-inductive ITER current drive operation with typically 50\% of the plasma current driven by the bootstrap effect (Green et al 2003 Plasma Phys. Control. Fusion 45 587). In addition, the existence domain of the advanced mode regimes is also mapped in terms of dimensionless plasmas physics quantities such as normalized Larmor radius, normalized collisionality, Mach number and ratio of ion to electron temperature. The gap between present day and future advanced tokamak experiments is quantitatively assessed in terms of these dimensionless parameters.",

keywords = "JET, plasma, fusion energy, fusion reactors, tokamak, internal transport barriers, ITER",

author = "X. Litaudon and E. Barbato and A. B{\'e}coulet and E.J. Doyle and T. Fujita and P. Gohil and F. Imbeaux and O. Sauter and G. Sips and J. Connor and E.J. Doyle and Yu Esipchuk and T. Fujita and T. Fukuda and P. Gohil and J. Kinsey and N. Kirneva and S. Lebedev and X. Litaudon and V. Mukhovatov and J. Rice and E. Synakowski and K. Toi and B. Unterberg and V. Vershkov and M. Wakatani and T. Aniel and Baranov, \{Yu F.\} and E. Barbato and A. B{\'e}coulet and R. Behn and C. Bourdelle and G. Bracco and R.V. Budny and P. Buratti and E.J. Doyle and Yu Esipchuk and B. Esposito and S. Ide and A.R. Field and T. Fujita and T. Fukuda and P. Gohil and C. Gormezano and C. Greenfield and M. Greenwald and T.S. Hahm and G.T. Hoang and J. Hobirk and D. Hogeweij and S. Ide and A. Isayama and F. Imbeaux and E. Joffrin and Y. Kamada and J. Kinsey and N. Kirneva and X. Litaudon and T.C. Luce and M. Murakami and V. Parail and Y-K.M. Peng and F. Ryter and Y. Sakamoto and H. Shirai and G. Sips and T. Suzuki and E. Synakowski and H. Takenaga and T. Takizuka and Tuomas Tala and M.R. Wade and J. Weiland",

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doi = "10.1088/0741-3335/46/5A/002",

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pages = "A19--A34",

journal = "Plasma Physics and Controlled Fusion",

issn = "0741-3335",

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Litaudon, X, Barbato, E, Bécoulet, A, Doyle, EJ, Fujita, T, Gohil, P, Imbeaux, F, Sauter, O, Sips, G, Connor, J, Doyle, EJ, Esipchuk, Y, Fujita, T, Fukuda, T, Gohil, P, Kinsey, J, Kirneva, N, Lebedev, S, Litaudon, X, Mukhovatov, V, Rice, J, Synakowski, E, Toi, K, Unterberg, B, Vershkov, V, Wakatani, M, Aniel, T, Baranov, YF, Barbato, E, Bécoulet, A, Behn, R, Bourdelle, C, Bracco, G, Budny, RV, Buratti, P, Doyle, EJ, Esipchuk, Y, Esposito, B, Ide, S, Field, AR, Fujita, T, Fukuda, T, Gohil, P, Gormezano, C, Greenfield, C, Greenwald, M, Hahm, TS, Hoang, GT, Hobirk, J, Hogeweij, D, Ide, S, Isayama, A, Imbeaux, F, Joffrin, E, Kamada, Y, Kinsey, J, Kirneva, N, Litaudon, X, Luce, TC, Murakami, M, Parail, V, Peng, Y-KM, Ryter, F, Sakamoto, Y, Shirai, H, Sips, G, Suzuki, T, Synakowski, E, Takenaga, H, Takizuka, T, Tala, T, Wade, MR & Weiland, J 2004, 'Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database', Plasma Physics and Controlled Fusion, vol. 46, no. 5A, pp. A19-A34. https://doi.org/10.1088/0741-3335/46/5A/002

TY - JOUR

T1 - Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database

AU - Litaudon, X.

AU - Barbato, E.

AU - Bécoulet, A.

AU - Doyle, E.J.

AU - Fujita, T.

AU - Gohil, P.

AU - Imbeaux, F.

AU - Sauter, O.

AU - Sips, G.

AU - Connor, J.

AU - Doyle, E.J.

AU - Esipchuk, Yu

AU - Fujita, T.

AU - Fukuda, T.

AU - Gohil, P.

AU - Kinsey, J.

AU - Kirneva, N.

AU - Lebedev, S.

AU - Litaudon, X.

AU - Mukhovatov, V.

AU - Rice, J.

AU - Synakowski, E.

AU - Toi, K.

AU - Unterberg, B.

AU - Vershkov, V.

AU - Wakatani, M.

AU - Aniel, T.

AU - Baranov, Yu F.

AU - Barbato, E.

AU - Bécoulet, A.

AU - Behn, R.

AU - Bourdelle, C.

AU - Bracco, G.

AU - Budny, R.V.

AU - Buratti, P.

AU - Doyle, E.J.

AU - Esipchuk, Yu

AU - Esposito, B.

AU - Ide, S.

AU - Field, A.R.

AU - Fujita, T.

AU - Fukuda, T.

AU - Gohil, P.

AU - Gormezano, C.

AU - Greenfield, C.

AU - Greenwald, M.

AU - Hahm, T.S.

AU - Hoang, G.T.

AU - Hobirk, J.

AU - Hogeweij, D.

AU - Ide, S.

AU - Isayama, A.

AU - Imbeaux, F.

AU - Joffrin, E.

AU - Kamada, Y.

AU - Kinsey, J.

AU - Kirneva, N.

AU - Litaudon, X.

AU - Luce, T.C.

AU - Murakami, M.

AU - Parail, V.

AU - Peng, Y-K.M.

AU - Ryter, F.

AU - Sakamoto, Y.

AU - Shirai, H.

AU - Sips, G.

AU - Suzuki, T.

AU - Synakowski, E.

AU - Takenaga, H.

AU - Takizuka, T.

AU - Tala, Tuomas

AU - Wade, M.R.

AU - Weiland, J.

PY - 2004

Y1 - 2004

N2 - Advanced tokamak regimes obtained in ASDEX Upgrade, DIII-D, FT-U, JET, JT-60U, TCV and Tore Supra experiments are assessed both in terms of their fusion performance and capability for ultimately reaching steady-state using data from the international internal transport barrier database. These advanced modes of tokamak operation are characterized by an improved core confinement and a modified current profile compared to the relaxed Ohmically driven one. The present results obtained in these experiments are studied in view of their prospect for achieving either long pulses ('hybrid' scenario with inductive and non-inductive current drive) or ultimately steady-state purely non-inductive current drive operation in next step devices such as ITER. A new operational diagram for advanced tokamak operation is proposed where the figure of merit characterizing the fusion performances and confinement, H × βN / q 295, is drawn versus the fraction of the plasma current driven by the bootstrap effect. In this diagram, present day advanced tokamak regimes have now reached an operational domain that is required in the non-inductive ITER current drive operation with typically 50% of the plasma current driven by the bootstrap effect (Green et al 2003 Plasma Phys. Control. Fusion 45 587). In addition, the existence domain of the advanced mode regimes is also mapped in terms of dimensionless plasmas physics quantities such as normalized Larmor radius, normalized collisionality, Mach number and ratio of ion to electron temperature. The gap between present day and future advanced tokamak experiments is quantitatively assessed in terms of these dimensionless parameters.

AB - Advanced tokamak regimes obtained in ASDEX Upgrade, DIII-D, FT-U, JET, JT-60U, TCV and Tore Supra experiments are assessed both in terms of their fusion performance and capability for ultimately reaching steady-state using data from the international internal transport barrier database. These advanced modes of tokamak operation are characterized by an improved core confinement and a modified current profile compared to the relaxed Ohmically driven one. The present results obtained in these experiments are studied in view of their prospect for achieving either long pulses ('hybrid' scenario with inductive and non-inductive current drive) or ultimately steady-state purely non-inductive current drive operation in next step devices such as ITER. A new operational diagram for advanced tokamak operation is proposed where the figure of merit characterizing the fusion performances and confinement, H × βN / q 295, is drawn versus the fraction of the plasma current driven by the bootstrap effect. In this diagram, present day advanced tokamak regimes have now reached an operational domain that is required in the non-inductive ITER current drive operation with typically 50% of the plasma current driven by the bootstrap effect (Green et al 2003 Plasma Phys. Control. Fusion 45 587). In addition, the existence domain of the advanced mode regimes is also mapped in terms of dimensionless plasmas physics quantities such as normalized Larmor radius, normalized collisionality, Mach number and ratio of ion to electron temperature. The gap between present day and future advanced tokamak experiments is quantitatively assessed in terms of these dimensionless parameters.

KW - JET

KW - plasma

KW - fusion energy

KW - fusion reactors

KW - tokamak

KW - internal transport barriers

KW - ITER

U2 - 10.1088/0741-3335/46/5A/002

DO - 10.1088/0741-3335/46/5A/002

M3 - Article

SN - 0741-3335

VL - 46

SP - A19-A34

JO - Plasma Physics and Controlled Fusion

JF - Plasma Physics and Controlled Fusion

IS - 5A

ER -

Status of and prospects for advanced tokamak regimes from multi-machine comparisons using the 'International Tokamak Physics Activity' database

Abstract

UN SDGs

Keywords

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