DIII-D research to provide solutions for ITER and fusion energy
No Thumbnail Available
Access rights
openAccess
publishedVersion
URL
Journal Title
Journal ISSN
Volume Title
A1 Alkuperäisartikkeli tieteellisessä aikakauslehdessä
This publication is imported from Aalto University research portal.
View publication in the Research portal (opens in new window)
View/Open full text file from the Research portal (opens in new window)
Other link related to publication (opens in new window)
View publication in the Research portal (opens in new window)
View/Open full text file from the Research portal (opens in new window)
Other link related to publication (opens in new window)
Date
2024-11
Department
Major/Subject
Mcode
Degree programme
Language
en
Pages
18
Series
Nuclear Fusion, Volume 64, issue 11, pp. 1-18
Abstract
The DIII-D tokamak has elucidated crucial physics and developed projectable solutions for ITER and fusion power plants in the key areas of core performance, boundary heat and particle transport, and integrated scenario operation, with closing the core-edge integration knowledge gap being the overarching mission. New experimental validation of high-fidelity, multi-channel, non-linear gyrokinetic turbulent transport models for ITER provides strong confidence it will achieve Q ≥ 10 operation. Experiments identify options for easing H-mode access in hydrogen, and give new insight into the isotopic dependence of transport and confinement. Analysis of 2,1 islands in unoptimized low-torque IBS demonstration discharges suggests their onset time occurs randomly in the constant β phase, most often triggered by non-linear 3-wave coupling, thus identifying an NTM seeding mechanism to avoid. Pure deuterium SPI for disruption mitigation is shown to provide favorable slow cooling, but poor core assimilation, suggesting paths for improved SPI on ITER. At the boundary, measured neutral density and ionization source fluxes are strongly poloidally asymmetric, implying a 2D treatment is needed to model pedestal fuelling. Detailed measurements of pedestal and SOL quantities and impurity charge state radiation in detached divertors has validated edge fluid modelling and new self-consistent ‘pedestal-to-divertor’ integrated modeling that can be used to optimize reactors. New feedback adaptive ELM control minimizes confinement reduction, and RMP ELM suppression with sustained high core performance was obtained for the first time with the outer strike point in a W-coated, compact and unpumped small-angle slot divertor. Advances have been made in integrated operational scenarios for ITER and power plants. Wide pedestal intrinsically ELM-free QH-modes are produced with more reactor-relevant conditions, Low torque IBS with W-equivalent radiators can exhibit predator-prey oscillations in Te and radiation which need control. High-βP scenarios with qmin > 2, q95–7.9, βN > 4, βT–3.3% and H98y2 > 1.5 are sustained with high density (n̄ = 7E19 m−3, fG–1) for 6 τE, improving confidence in steady-state tokamak reactors. Diverted NT plasmas achieve high core performance with a non-ELMing edge, offering a possible highly attractive core-edge integration solution for reactors.Description
Publisher Copyright: © 2024 The Author(s).
Keywords
DIII-D, overview, tokamak
Other note
Citation
Ahmed, S, Anderson, J, Chen, J, Chen, R, Chen, J, Chen, X, Chen, Y, Choi, W, Chowdhury, S, Ding, R, Du, X, Groth, M, Guo, H, Han, X, Holm, A, Hu, Y, Hu, Q, Huang, Y, Huang, J, Huang, A, Jarvinen, A, Jiang, Y, Johnson, J, Jones, M, Kim, J, Kim, H, Kim, S, Kim, K, Kim, C, Kim, T, Kumar, N, Lee, S, Lee, K, Li, G, Li, X, Li, Y, Li, L, Li, Z, Lin, Z, Lin, Z, Lin, Y, Liu, J, Liu, D, Liu, C, Liu, Z, Liu, Y, Liu, C, Ma, X, Mohamed, M, Nguyen, P, Nguyen, D, Pan, C, Park, J, Park, J, Qian, J, Qin, X, Ross, M, Salmi, A, Shen, H, Smith, S, Smith, D, Song, X, Su, D, Sun, P, Sun, Y, Sun, Y, Suzuki, Y, Tang, S, Tang, S, Truong, D, Wang, L, Wang, Y, Wang, H, Wang, Z, Wang, A, Wei, X, Xie, R, Xu, G, Xu, X, Yan, Z, Yang, X, Yang, L, Yang, S, Yang, J, Yu, J, Zhang, X, Zhang, J, Zhang, B, Zhang, J, Zhao, B, Zheng, Y, Zhu, Y, Zhu, J & DIII-D Team 2024, ' DIII-D research to provide solutions for ITER and fusion energy ', Nuclear Fusion, vol. 64, no. 11, 112003, pp. 1-18 . https://doi.org/10.1088/1741-4326/ad2fe9