Evolution of radiation profiles in a strongly baffled divertor on MAST Upgrade
Plasma detachment in tokamaks is necessary in future tokamaks to sufficiently reduce the heat flux to the target. It involves interactions of the plasma with impurities and neutral particles, leading to significant losses of plasma power, momentum, and particles. An accurate mapping of plasma emissivity in the divertor and X-point region is essential to localise and infer the power losses influencing the detachment process. The recently validated InfraRed Video Bolometer (IRVB) diagnostic, in MAST-U (Federici et al., 2023), enables this mapping with higher spatial resolution than more established methods like resistive bolometers. In previous preliminary work (Federici et al., 2023a)[2], the detachment of the radiation from the target (radiative detachment) was characterised in L-mode (power entering the scrape-off layer, P S O L ∼ 0.4 MW). With a conventional divertor the inner leg consistently detached ahead of the outer leg, and radiative detachment preceded particle flux detachment. This work presents results also from the third MAST-U experimental campaign, fuelled from the low field side instead of the high field side, including Ohmic and beam heated L-mode shots (with a power exiting the core up to P S O L ∼ 1–1.5 MW). The radiation peak moves upstream from the target at lower upstream densities than the ion target flux roll-over (typically considered the detachment onset), while radiation on the inner leg detaches before the outer one in high field side fuelled shots and about at the same time in low field side fuelled ones. The movement of the radiation is in partial agreement with the expectations from the DLS model (Myatra, 2021; Cowley et al., 2022; Lipschultz et al., 2016), predicting a sudden shift from the target to the X-point on the inner leg. The energy confinement is found to be related to detachment, but there seems to be some margin between the radiation peak caused by impurity radiation reaching the X-point and confinement being affected, a beneficial characteristic if it could be extrapolated to future reactors. For increasing P S O L the particle flux roll over happens for similar upstream densities. Comparing the total radiated power with the D 2 Fulcher band emission evolution shows that in a conventional divertor a significant fraction of the radiated power is due to carbon radiation (outside of the divertor chamber). • For the first time published radiation maps from the novel IRVB diagnostic in MASTU. • Radiation observed in MASTU, a spherical tokamak, to detach in a similar manner as in conventional aspect ratio tokamaks. • Detachment of the radiation peak in both legs occurs at a lower upstream density than particle flux detachment. • High field side fuelling causes local cooling of the separatrix and negatively effects detachment and core performance. • With low field side fuelling the 50% falloff radiation marker detaches for the same upstream density in the double null conventional divertor configuration examined. • Significant impurity radiation can be present near the X-point without negatively affecting core confinement, but particle flux roll over does. • The movement of the radiation on the inner and outer legs is consistent with predictions from the DLS model. The radiation transitions sharply from the target to the X-point on the inner leg, while this is gradual on the outer leg. • Comparing total radiation with D2 Fulcher emission can inform on the relative importance of impurity compared to hydrogenic radiation. • The peak of total radiation is mostly related to impurity radiation while the 50% falloff marker with hydrogenic radiation and the detachment of the ionisation front.
Authors
- Mike Kryjak
- F. Federici
- Jeremy D. Lore (ORCID: https://orcid.org/0000-0002-9192-465X)
- J. Harrison (ORCID: https://orcid.org/0000-0003-2906-5097)
- P. Ryan (ORCID: https://orcid.org/0000-0002-7133-6156)
- B. Lipschultz
- A. Thornton (ORCID: https://orcid.org/0000-0002-7155-230X)
- B. Lomanowski (ORCID: https://orcid.org/0000-0003-2226-2004)
- Matthew L. Reinke (ORCID: https://orcid.org/0000-0003-4413-9613)
- C. Cowley (ORCID: https://orcid.org/0000-0001-7065-8922)
- N. Lonigro (ORCID: https://orcid.org/0000-0001-8581-0384)
- J. Lovell (ORCID: https://orcid.org/0000-0001-9565-3466)
- Y. Damizia
- K. Verhaegh (ORCID: https://orcid.org/0000-0002-0500-2764)
- Byron J. Peterson
Institutions
- Oak Ridge National Laboratory (US)
- University of Liverpool (GB)
- University of Exeter (GB)
- Culham Centre for Fusion Energy (GB)
- National Institute for Fusion Science (JP)
- Boston Fusion (United States) (US)
- University of York (GB)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2025-05-02
- DOI
- https://doi.org/10.1016/j.nme.2025.101940
- Citations
- 2
- Primary Topic
- Magnetic confinement fusion research
- Type
- article
- Field-Weighted Citation Impact
- 3.74
Funders
- U.S. Department of Energy
- European Commission
- Euratom Research and Training Programme
- Engineering and Physical Sciences Research Council
- Fusion Energy Sciences