Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade

J. Rapp, A. Kallenbach, R. Neu, T. Eich, R. Fischer, A. Herrmann, S. Potzel, G.J. Rooij, van, J.J. Zielinski

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Abstract

The type-III ELMy H-mode might be the solution for an integrated ITER operation scenario fulfilling the fusion power amplification factor (output fusion power to input heating power) of Q = 10 with simultaneous acceptable steady-state and transient power loads to the plasma-facing components. This highly radiative type-III ELMy H-mode is achieved by nitrogen seeding. Experiments on the tokamak ASDEX Upgrade, in which all plasma-facing components are coated with tungsten, showed favourable confinement conditions (H98(y,2) = 1) at high plasma pressure (ßN = 2.4). The power load to the plasma-facing components is as low as ˜3MWm-2 during the peak heat loads due to edge localized modes (ELMs) at high radiative power fractions of frad ˜ 0.75. In those high-density discharges the central impurity concentration is very low as a result of hollow nitrogen density profiles and minimal erosion of tungsten. The tungsten erosion is not only suppressed in between ELMs, when the divertor is detached, but also during the type-III ELM activity. Such low impurity concentrations in the plasma core might lead to even higher fusion amplification factors in ITER than 10. This is a demonstration of the compatibility of the radiating type-III ELMy H-mode with a tungsten divertor and main chamber wall, with sufficient confinement and favourable power exhaust characteristics. Together with previous results in all-carbon devices this demonstration strengthens the case for a potential application of a Q = 10 scenario on ITER.
LanguageEnglish
Article number122002
Pages122002-1/4
Number of pages4
JournalNuclear Fusion
Volume52
Issue number12
DOIs
StatePublished - 2012

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tungsten
fusion
nitrogen
impurities
inoculation
compatibility
erosion
hollow
chambers
heating
output
carbon
profiles

Cite this

Rapp, J., Kallenbach, A., Neu, R., Eich, T., Fischer, R., Herrmann, A., ... Zielinski, J. J. (2012). Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade. Nuclear Fusion, 52(12), 122002-1/4. [122002]. DOI: 10.1088/0029-5515/52/12/122002
Rapp, J. ; Kallenbach, A. ; Neu, R. ; Eich, T. ; Fischer, R. ; Herrmann, A. ; Potzel, S. ; Rooij, van, G.J. ; Zielinski, J.J./ Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade. In: Nuclear Fusion. 2012 ; Vol. 52, No. 12. pp. 122002-1/4
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author = "J. Rapp and A. Kallenbach and R. Neu and T. Eich and R. Fischer and A. Herrmann and S. Potzel and {Rooij, van}, G.J. and J.J. Zielinski",
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Rapp, J, Kallenbach, A, Neu, R, Eich, T, Fischer, R, Herrmann, A, Potzel, S, Rooij, van, GJ & Zielinski, JJ 2012, 'Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade' Nuclear Fusion, vol. 52, no. 12, 122002, pp. 122002-1/4. DOI: 10.1088/0029-5515/52/12/122002

Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade. / Rapp, J.; Kallenbach, A.; Neu, R.; Eich, T.; Fischer, R.; Herrmann, A.; Potzel, S.; Rooij, van, G.J.; Zielinski, J.J.

In: Nuclear Fusion, Vol. 52, No. 12, 122002, 2012, p. 122002-1/4.

Research output: Contribution to journalArticleAcademicpeer-review

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T1 - Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade

AU - Rapp,J.

AU - Kallenbach,A.

AU - Neu,R.

AU - Eich,T.

AU - Fischer,R.

AU - Herrmann,A.

AU - Potzel,S.

AU - Rooij, van,G.J.

AU - Zielinski,J.J.

PY - 2012

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N2 - The type-III ELMy H-mode might be the solution for an integrated ITER operation scenario fulfilling the fusion power amplification factor (output fusion power to input heating power) of Q = 10 with simultaneous acceptable steady-state and transient power loads to the plasma-facing components. This highly radiative type-III ELMy H-mode is achieved by nitrogen seeding. Experiments on the tokamak ASDEX Upgrade, in which all plasma-facing components are coated with tungsten, showed favourable confinement conditions (H98(y,2) = 1) at high plasma pressure (ßN = 2.4). The power load to the plasma-facing components is as low as ˜3MWm-2 during the peak heat loads due to edge localized modes (ELMs) at high radiative power fractions of frad ˜ 0.75. In those high-density discharges the central impurity concentration is very low as a result of hollow nitrogen density profiles and minimal erosion of tungsten. The tungsten erosion is not only suppressed in between ELMs, when the divertor is detached, but also during the type-III ELM activity. Such low impurity concentrations in the plasma core might lead to even higher fusion amplification factors in ITER than 10. This is a demonstration of the compatibility of the radiating type-III ELMy H-mode with a tungsten divertor and main chamber wall, with sufficient confinement and favourable power exhaust characteristics. Together with previous results in all-carbon devices this demonstration strengthens the case for a potential application of a Q = 10 scenario on ITER.

AB - The type-III ELMy H-mode might be the solution for an integrated ITER operation scenario fulfilling the fusion power amplification factor (output fusion power to input heating power) of Q = 10 with simultaneous acceptable steady-state and transient power loads to the plasma-facing components. This highly radiative type-III ELMy H-mode is achieved by nitrogen seeding. Experiments on the tokamak ASDEX Upgrade, in which all plasma-facing components are coated with tungsten, showed favourable confinement conditions (H98(y,2) = 1) at high plasma pressure (ßN = 2.4). The power load to the plasma-facing components is as low as ˜3MWm-2 during the peak heat loads due to edge localized modes (ELMs) at high radiative power fractions of frad ˜ 0.75. In those high-density discharges the central impurity concentration is very low as a result of hollow nitrogen density profiles and minimal erosion of tungsten. The tungsten erosion is not only suppressed in between ELMs, when the divertor is detached, but also during the type-III ELM activity. Such low impurity concentrations in the plasma core might lead to even higher fusion amplification factors in ITER than 10. This is a demonstration of the compatibility of the radiating type-III ELMy H-mode with a tungsten divertor and main chamber wall, with sufficient confinement and favourable power exhaust characteristics. Together with previous results in all-carbon devices this demonstration strengthens the case for a potential application of a Q = 10 scenario on ITER.

U2 - 10.1088/0029-5515/52/12/122002

DO - 10.1088/0029-5515/52/12/122002

M3 - Article

VL - 52

SP - 122002-1/4

JO - Nuclear Fusion

T2 - Nuclear Fusion

JF - Nuclear Fusion

SN - 0029-5515

IS - 12

M1 - 122002

ER -

Rapp J, Kallenbach A, Neu R, Eich T, Fischer R, Herrmann A et al. Radiative type-III ELMy H-mode in all-tungsten ASDEX Upgrade. Nuclear Fusion. 2012;52(12):122002-1/4. 122002. Available from, DOI: 10.1088/0029-5515/52/12/122002