Development of advanced inductive scenarios for ITER

T.C. Luce, C. D. Challis, S. Ide, E. Joffrin, Y. Kamada, P.A. Politzer, J. Schweinzer, A.C.C. Sips, J. Stober, G. Giruzzi, C.E. Kessel, M. Murakami, Y. S. Na, J.M. Park, A.R. Polevoi, R.V. Budny, J. Citrin, J. Garcia, N. Nayashi, J. HobirkB.F. Hudson, F. Imbeaux, A. Isayama, D.C. McDonald, T. Nakano, N. Oyama, V.V. Parail, T.W. Petrie, C.C. Petty, T. Suzuki, M.R. Wade

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Abstract

Since its inception in 2002, the International Tokamak Physics Activity topical group on Integrated Operational Scenarios (IOS) has coordinated experimental and modelling activity on the development of advanced inductive scenarios for applications in the ITER tokamak. The physics basis and the prospects for applications in ITER have been advanced significantly during that time, especially with respect to experimental results. The principal findings of this research activity are as follows. Inductive scenarios capable of higher normalized pressure (ßN 2.4) than the ITER baseline scenario (ßN = 1.8) with normalized confinement at or above the standard H-mode scaling are well established under stationary conditions on the four largest diverted tokamaks (AUG, DIII-D, JET, JT-60U), demonstrated in a database of more than 500 plasmas from these tokamaks analysed here. The parameter range where high performance is achieved is broad in q95 and density normalized to the empirical density limit. MHD modes can play a key role in reaching stationary high performance, but also define the limits to achieved stability and confinement. Projection of performance in ITER from existing experiments uses empirical scalings and theory-based modelling. The status of the experimental validation of both approaches is summarized here. The database shows significant variation in the energy confinement normalized to standard H-mode confinement scalings, indicating the possible influence of additional physics variables absent from the scalings. Tests using the available information on rotation and the ratio of the electron and ion temperatures indicate neither of these variables in isolation can explain the variation in normalized confinement observed. Trends in the normalized confinement with the two dimensionless parameters that vary most from present-day experiments to ITER, gyroradius and collision frequency, are significant. Regression analysis on the multi-tokamak database has been performed, but it appears that the database is not conditioned sufficiently well to yield a new scaling for this type of plasma. Coordinated experiments on size scaling using the dimensionless parameter scaling approach find a weaker scaling with normalized gyroradius than the standard H-mode scaling. Preliminary studies on scaling with collision frequency show a favourable scaling stronger than the standard H-mode scaling. Coordinated modelling activity has resulted in successful benchmarking of modelling codes in the ITER regime. Validation of transport models using these codes on present-day experiments is in progress, but no single model has been shown to capture the variations seen in the experiments. However, projection to ITER using these models is in general agreement with the favourable projections found with the empirical scalings.
Original languageEnglish
Article number013015
Pages (from-to)013015-1/15
Number of pages15
JournalNuclear Fusion
Volume54
Issue number1
DOIs
Publication statusPublished - 2013

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scaling
projection
physics
collisions
ion temperature
regression analysis
isolation
trends

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Luce, T. C., Challis, C. D., Ide, S., Joffrin, E., Kamada, Y., Politzer, P. A., ... Wade, M. R. (2013). Development of advanced inductive scenarios for ITER. Nuclear Fusion, 54(1), 013015-1/15. [013015]. https://doi.org/doi:10.1088/0029-5515/54/1/013015
Luce, T.C. ; Challis, C. D. ; Ide, S. ; Joffrin, E. ; Kamada, Y. ; Politzer, P.A. ; Schweinzer, J. ; Sips, A.C.C. ; Stober, J. ; Giruzzi, G. ; Kessel, C.E. ; Murakami, M. ; Na, Y. S. ; Park, J.M. ; Polevoi, A.R. ; Budny, R.V. ; Citrin, J. ; Garcia, J. ; Nayashi, N. ; Hobirk, J. ; Hudson, B.F. ; Imbeaux, F. ; Isayama, A. ; McDonald, D.C. ; Nakano, T. ; Oyama, N. ; Parail, V.V. ; Petrie, T.W. ; Petty, C.C. ; Suzuki, T. ; Wade, M.R. / Development of advanced inductive scenarios for ITER. In: Nuclear Fusion. 2013 ; Vol. 54, No. 1. pp. 013015-1/15.
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abstract = "Since its inception in 2002, the International Tokamak Physics Activity topical group on Integrated Operational Scenarios (IOS) has coordinated experimental and modelling activity on the development of advanced inductive scenarios for applications in the ITER tokamak. The physics basis and the prospects for applications in ITER have been advanced significantly during that time, especially with respect to experimental results. The principal findings of this research activity are as follows. Inductive scenarios capable of higher normalized pressure ({\ss}N 2.4) than the ITER baseline scenario ({\ss}N = 1.8) with normalized confinement at or above the standard H-mode scaling are well established under stationary conditions on the four largest diverted tokamaks (AUG, DIII-D, JET, JT-60U), demonstrated in a database of more than 500 plasmas from these tokamaks analysed here. The parameter range where high performance is achieved is broad in q95 and density normalized to the empirical density limit. MHD modes can play a key role in reaching stationary high performance, but also define the limits to achieved stability and confinement. Projection of performance in ITER from existing experiments uses empirical scalings and theory-based modelling. The status of the experimental validation of both approaches is summarized here. The database shows significant variation in the energy confinement normalized to standard H-mode confinement scalings, indicating the possible influence of additional physics variables absent from the scalings. Tests using the available information on rotation and the ratio of the electron and ion temperatures indicate neither of these variables in isolation can explain the variation in normalized confinement observed. Trends in the normalized confinement with the two dimensionless parameters that vary most from present-day experiments to ITER, gyroradius and collision frequency, are significant. Regression analysis on the multi-tokamak database has been performed, but it appears that the database is not conditioned sufficiently well to yield a new scaling for this type of plasma. Coordinated experiments on size scaling using the dimensionless parameter scaling approach find a weaker scaling with normalized gyroradius than the standard H-mode scaling. Preliminary studies on scaling with collision frequency show a favourable scaling stronger than the standard H-mode scaling. Coordinated modelling activity has resulted in successful benchmarking of modelling codes in the ITER regime. Validation of transport models using these codes on present-day experiments is in progress, but no single model has been shown to capture the variations seen in the experiments. However, projection to ITER using these models is in general agreement with the favourable projections found with the empirical scalings.",
author = "T.C. Luce and Challis, {C. D.} and S. Ide and E. Joffrin and Y. Kamada and P.A. Politzer and J. Schweinzer and A.C.C. Sips and J. Stober and G. Giruzzi and C.E. Kessel and M. Murakami and Na, {Y. S.} and J.M. Park and A.R. Polevoi and R.V. Budny and J. Citrin and J. Garcia and N. Nayashi and J. Hobirk and B.F. Hudson and F. Imbeaux and A. Isayama and D.C. McDonald and T. Nakano and N. Oyama and V.V. Parail and T.W. Petrie and C.C. Petty and T. Suzuki and M.R. Wade",
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Luce, TC, Challis, CD, Ide, S, Joffrin, E, Kamada, Y, Politzer, PA, Schweinzer, J, Sips, ACC, Stober, J, Giruzzi, G, Kessel, CE, Murakami, M, Na, YS, Park, JM, Polevoi, AR, Budny, RV, Citrin, J, Garcia, J, Nayashi, N, Hobirk, J, Hudson, BF, Imbeaux, F, Isayama, A, McDonald, DC, Nakano, T, Oyama, N, Parail, VV, Petrie, TW, Petty, CC, Suzuki, T & Wade, MR 2013, 'Development of advanced inductive scenarios for ITER', Nuclear Fusion, vol. 54, no. 1, 013015, pp. 013015-1/15. https://doi.org/doi:10.1088/0029-5515/54/1/013015

Development of advanced inductive scenarios for ITER. / Luce, T.C.; Challis, C. D.; Ide, S.; Joffrin, E.; Kamada, Y.; Politzer, P.A.; Schweinzer, J.; Sips, A.C.C.; Stober, J.; Giruzzi, G.; Kessel, C.E.; Murakami, M.; Na, Y. S.; Park, J.M.; Polevoi, A.R.; Budny, R.V.; Citrin, J.; Garcia, J.; Nayashi, N.; Hobirk, J.; Hudson, B.F.; Imbeaux, F.; Isayama, A.; McDonald, D.C.; Nakano, T.; Oyama, N.; Parail, V.V.; Petrie, T.W.; Petty, C.C.; Suzuki, T.; Wade, M.R.

In: Nuclear Fusion, Vol. 54, No. 1, 013015, 2013, p. 013015-1/15.

Research output: Contribution to journalArticleAcademicpeer-review

TY - JOUR

T1 - Development of advanced inductive scenarios for ITER

AU - Luce, T.C.

AU - Challis, C. D.

AU - Ide, S.

AU - Joffrin, E.

AU - Kamada, Y.

AU - Politzer, P.A.

AU - Schweinzer, J.

AU - Sips, A.C.C.

AU - Stober, J.

AU - Giruzzi, G.

AU - Kessel, C.E.

AU - Murakami, M.

AU - Na, Y. S.

AU - Park, J.M.

AU - Polevoi, A.R.

AU - Budny, R.V.

AU - Citrin, J.

AU - Garcia, J.

AU - Nayashi, N.

AU - Hobirk, J.

AU - Hudson, B.F.

AU - Imbeaux, F.

AU - Isayama, A.

AU - McDonald, D.C.

AU - Nakano, T.

AU - Oyama, N.

AU - Parail, V.V.

AU - Petrie, T.W.

AU - Petty, C.C.

AU - Suzuki, T.

AU - Wade, M.R.

PY - 2013

Y1 - 2013

N2 - Since its inception in 2002, the International Tokamak Physics Activity topical group on Integrated Operational Scenarios (IOS) has coordinated experimental and modelling activity on the development of advanced inductive scenarios for applications in the ITER tokamak. The physics basis and the prospects for applications in ITER have been advanced significantly during that time, especially with respect to experimental results. The principal findings of this research activity are as follows. Inductive scenarios capable of higher normalized pressure (ßN 2.4) than the ITER baseline scenario (ßN = 1.8) with normalized confinement at or above the standard H-mode scaling are well established under stationary conditions on the four largest diverted tokamaks (AUG, DIII-D, JET, JT-60U), demonstrated in a database of more than 500 plasmas from these tokamaks analysed here. The parameter range where high performance is achieved is broad in q95 and density normalized to the empirical density limit. MHD modes can play a key role in reaching stationary high performance, but also define the limits to achieved stability and confinement. Projection of performance in ITER from existing experiments uses empirical scalings and theory-based modelling. The status of the experimental validation of both approaches is summarized here. The database shows significant variation in the energy confinement normalized to standard H-mode confinement scalings, indicating the possible influence of additional physics variables absent from the scalings. Tests using the available information on rotation and the ratio of the electron and ion temperatures indicate neither of these variables in isolation can explain the variation in normalized confinement observed. Trends in the normalized confinement with the two dimensionless parameters that vary most from present-day experiments to ITER, gyroradius and collision frequency, are significant. Regression analysis on the multi-tokamak database has been performed, but it appears that the database is not conditioned sufficiently well to yield a new scaling for this type of plasma. Coordinated experiments on size scaling using the dimensionless parameter scaling approach find a weaker scaling with normalized gyroradius than the standard H-mode scaling. Preliminary studies on scaling with collision frequency show a favourable scaling stronger than the standard H-mode scaling. Coordinated modelling activity has resulted in successful benchmarking of modelling codes in the ITER regime. Validation of transport models using these codes on present-day experiments is in progress, but no single model has been shown to capture the variations seen in the experiments. However, projection to ITER using these models is in general agreement with the favourable projections found with the empirical scalings.

AB - Since its inception in 2002, the International Tokamak Physics Activity topical group on Integrated Operational Scenarios (IOS) has coordinated experimental and modelling activity on the development of advanced inductive scenarios for applications in the ITER tokamak. The physics basis and the prospects for applications in ITER have been advanced significantly during that time, especially with respect to experimental results. The principal findings of this research activity are as follows. Inductive scenarios capable of higher normalized pressure (ßN 2.4) than the ITER baseline scenario (ßN = 1.8) with normalized confinement at or above the standard H-mode scaling are well established under stationary conditions on the four largest diverted tokamaks (AUG, DIII-D, JET, JT-60U), demonstrated in a database of more than 500 plasmas from these tokamaks analysed here. The parameter range where high performance is achieved is broad in q95 and density normalized to the empirical density limit. MHD modes can play a key role in reaching stationary high performance, but also define the limits to achieved stability and confinement. Projection of performance in ITER from existing experiments uses empirical scalings and theory-based modelling. The status of the experimental validation of both approaches is summarized here. The database shows significant variation in the energy confinement normalized to standard H-mode confinement scalings, indicating the possible influence of additional physics variables absent from the scalings. Tests using the available information on rotation and the ratio of the electron and ion temperatures indicate neither of these variables in isolation can explain the variation in normalized confinement observed. Trends in the normalized confinement with the two dimensionless parameters that vary most from present-day experiments to ITER, gyroradius and collision frequency, are significant. Regression analysis on the multi-tokamak database has been performed, but it appears that the database is not conditioned sufficiently well to yield a new scaling for this type of plasma. Coordinated experiments on size scaling using the dimensionless parameter scaling approach find a weaker scaling with normalized gyroradius than the standard H-mode scaling. Preliminary studies on scaling with collision frequency show a favourable scaling stronger than the standard H-mode scaling. Coordinated modelling activity has resulted in successful benchmarking of modelling codes in the ITER regime. Validation of transport models using these codes on present-day experiments is in progress, but no single model has been shown to capture the variations seen in the experiments. However, projection to ITER using these models is in general agreement with the favourable projections found with the empirical scalings.

U2 - doi:10.1088/0029-5515/54/1/013015

DO - doi:10.1088/0029-5515/54/1/013015

M3 - Article

VL - 54

SP - 013015-1/15

JO - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 1

M1 - 013015

ER -

Luce TC, Challis CD, Ide S, Joffrin E, Kamada Y, Politzer PA et al. Development of advanced inductive scenarios for ITER. Nuclear Fusion. 2013;54(1):013015-1/15. 013015. https://doi.org/doi:10.1088/0029-5515/54/1/013015