TY - JOUR
T1 - First DIII-D-WEST hybrid scenario similarity experiments for ITER-relevant long-pulse operation
AU - the WEST Team
AU - DIII-D Team
AU - Litaudon, X.
AU - Ding, S.
AU - Kim, S.
AU - Lerche, E.
AU - Manas, P.
AU - Odstrčil, T.
AU - Sgrelli, D.
AU - Turco, F.
AU - Victor, B.
AU - Biwole, A. S.T.
AU - Boyes, W. S.
AU - Casali, L.
AU - Cazabonne, J.
AU - Gallo, A.
AU - Lunsford, R.
AU - Maget, P.
AU - Marinoni, A.
AU - Morales, J.
AU - Osborne, T. H.
AU - Park, J. M.
AU - Quadri, V.
AU - Savoye-Peysson, Y.
AU - Weldon, D.
N1 - Publisher Copyright:
© 2026 The Author(s). Published by IOP Publishing Ltd. Original content from this work may be used under the terms of the https://creativecommons.org/licenses/by/4.0/. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI.
PY - 2026/5
Y1 - 2026/5
N2 - For the first time, similarity experiments between DIII-D and WEST1414WEST, stands for ‘Tungsten (chemical symbol ‘W’) Environment in Steady-state Tokamak were performed in the ITER ‘hybrid-like’ regime during dedicated campaigns in April and May 2025. The matched parameters include elongation, triangularity, ion ∇B drift direction toward the X-point, q-profile, and core normalized physics quantities in terms of normalized pressure, normalized gyroradius, electron collisionality, ratio of ion to electron temperature, Ti/Te. Core transport physics is explored with different aspect ratio (R/a) values (typically 3 at DIII-D and 5 on WEST). DIII-D explored high-beta conditions (electromagnetic effect) with low torque injection (∼0 ± 0.5 N·m) using high heating power (up to 6 MW NBI and 2 MW electron cyclotron resonance heating powers), while scanning the heating mix (ion vs electron), beta, Ti/Te, core radiation via controlled tungsten injection using the laser blow-off system. WEST extended operation toward long-duration pulses using its actively cooled tungsten divertor, achieving dominated electron heating regimes with reduced tungsten contamination. Boron impurity injection were scanned on WEST to control edge conditions and core performance. It is found that core confinement improves—manifested by higher electron temperature, total energy content, neutron rate, and ion temperature—under conditions of low separatrix density, consistent with previous observations Bourdelle et al (2023 Nucl. Fusion 63 056021). Conditions for H-mode access and for ion heating in electron-dominated regimes in both WEST and DIII-D are discussed and compared. The ratio of the thermal energy confinement time (τE) to the volume-averaged electron–ion collisional heat exchange time (τe–i) is a key parameter to enhance ion heating and potentially facilitate H-mode access in electron-heated regimes. These first-of-a-kind coordinated DIII-D and WEST experiments provide a unique multi-machine dataset to validate predictive models and to optimize ITER hybrid-scenario performance under diverse core and edge conditions.
AB - For the first time, similarity experiments between DIII-D and WEST1414WEST, stands for ‘Tungsten (chemical symbol ‘W’) Environment in Steady-state Tokamak were performed in the ITER ‘hybrid-like’ regime during dedicated campaigns in April and May 2025. The matched parameters include elongation, triangularity, ion ∇B drift direction toward the X-point, q-profile, and core normalized physics quantities in terms of normalized pressure, normalized gyroradius, electron collisionality, ratio of ion to electron temperature, Ti/Te. Core transport physics is explored with different aspect ratio (R/a) values (typically 3 at DIII-D and 5 on WEST). DIII-D explored high-beta conditions (electromagnetic effect) with low torque injection (∼0 ± 0.5 N·m) using high heating power (up to 6 MW NBI and 2 MW electron cyclotron resonance heating powers), while scanning the heating mix (ion vs electron), beta, Ti/Te, core radiation via controlled tungsten injection using the laser blow-off system. WEST extended operation toward long-duration pulses using its actively cooled tungsten divertor, achieving dominated electron heating regimes with reduced tungsten contamination. Boron impurity injection were scanned on WEST to control edge conditions and core performance. It is found that core confinement improves—manifested by higher electron temperature, total energy content, neutron rate, and ion temperature—under conditions of low separatrix density, consistent with previous observations Bourdelle et al (2023 Nucl. Fusion 63 056021). Conditions for H-mode access and for ion heating in electron-dominated regimes in both WEST and DIII-D are discussed and compared. The ratio of the thermal energy confinement time (τE) to the volume-averaged electron–ion collisional heat exchange time (τe–i) is a key parameter to enhance ion heating and potentially facilitate H-mode access in electron-heated regimes. These first-of-a-kind coordinated DIII-D and WEST experiments provide a unique multi-machine dataset to validate predictive models and to optimize ITER hybrid-scenario performance under diverse core and edge conditions.
KW - DIII-D
KW - WEST
KW - fusion energy
KW - long pulse operation
KW - similarity experiments
KW - tokamak
UR - https://www.scopus.com/pages/publications/105038702653
UR - https://www.scopus.com/pages/publications/105038702653#tab=citedBy
U2 - 10.1088/1361-6587/ae5adb
DO - 10.1088/1361-6587/ae5adb
M3 - Article
AN - SCOPUS:105038702653
SN - 0741-3335
VL - 68
JO - Plasma Physics and Controlled Fusion
JF - Plasma Physics and Controlled Fusion
IS - 5
ER -