Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices
Name
22ja106_full.pdf
Size
4.42 MB
Format
Adobe PDF
Checksum (MD5)
250b065d95812737c4aafa5ea08e9dc4
Author(s)
Viezzer, E.
Austin, M.E.
Bernert, M.
Burrell, K.H.
Cano-Megias, P.
Chen, X.
Cruz-Zabala, D.J.
Coda, S.
Faitsch, M.
Fevrier, O.
Date Issued
August 2022
Journal
Nuclear Materials and Energy
Publisher
Elsevier
Abstract
One of our grand challenges towards fusion energy is the achievement of a high-performance plasma core coupled to a boundary solution. The high confinement mode (H-mode) provides such a high-performance fusion core due to the build-up of an edge transport barrier leading to a pedestal. However, it usually features type-I edge localized modes (ELMs) which pose a threat for long-duration plasma operation in future fusion devices as they induce large energy fluences onto the plasma facing components and typically are projected to damage the first wall. For future fusion devices, the integration of a stationary no-ELM regime with a power exhaust solution is indis- pensable. Several no-ELM and small-ELM regimes have extended their operational space in the past years, with the ultimate goal of providing an alternative core-edge solution to ITER and EU-DEMO. Prominent no-ELM or small-ELM alternatives include the I-mode, QH-mode, EDA H-mode, quasi-continuous exhaust (QCE) and ‘grassy’ ELM regimes, X-point radiator scenarios and negative triangularity L-mode. The state-of-the-art, including access conditions and main signatures, of these alternative regimes is reviewed. Many of these regimes partly match the operational space of ITER and EU-DEMO, however, knowledge gaps remain. Besides compatibility with divertor detachment and a radiative mantle, these include extrapolations to high Q operations, low core collisionality, high Greenwald fractions, impurity transport, amongst others. The knowledge gaps and possible strategies to close these gaps to show their applicability to ITER and EU-DEMO are discussed.
Description
Submitted for publication in Nuclear Materials and Energy
MIT Department
Massachusetts Institute of Technology. Plasma Science and Fusion Center
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1016/j.nme.2022.101308
