Published 2024 | Version v1
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Assimilation of deuterium into relativistic runaway electron beams and the implications for benign terminations in present devices, ITER, and future devices

  • 1. UCSD, La Jolla (United States)

Description

Localized wall damage from post-disruption runaway electron (RE) wall impact is a significant concern for future large tokamaks. One possible method for reducing this wall damage in the event of an unavoidable RE-wall impact is massive injection of low-Z (H2 or D2) gas. This injection can have the effect of partially recombining the cold thermal background plasma, resulting in a greatly increased RE final loss instability MHD amplitude, larger RE wetted area, and reduced local RE heat flux and damage. Experimental trends in thermal plasma partial recombination resulting from massive D2 injection into high-Z (Ar) containing runaway electron (RE) plateaus in DIII-D and JET were studied with the goal of understanding the parameters needed to achieve sufficiently low electron density (ne≈1018/m3) to increase the RE final loss MHD levels. In both DIII-D and JET, thermal electron density ne is found to drop by ~ 100× when the thermal plasma partially recombines, with a minimum at a vacuum vessel-averaged D2 density in the range 1020-1021/m3. RE effective resistivity also drops after partial recombination, indicating expulsion of the Ar content. Achieving partial recombination is found to become more difficult as RE current is increased. The amount of initial Ar in the RE plateau is not observed to have a strong effect on partial recombination. Partial recombination timescales of order 5 ms in DIII-D and 15 ms in JET are observed. These basic trends and timescales are matched with a 1D diffusion model, which is then used to extrapolate to ITER and SPARC tokamaks. It is predicted that ITER will be able to achieve sufficiently low ne values on time scales faster than expected RE plateau vertical drift timescales (of order 100 ms), provided sufficient D2 or H2 is injected. In SPARC, it is predicted that achieving significant ne recombination will be challenging, due to the very high RE current density. In both ITER and SPARC, it is predicted that achieving low ne will be easier with Ar as a background impurity (rather than Ne).

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Third Technical Meeting on Plasma Disruptions and their Mitigation. Presentations

Additional details

Publishing Information

Imprint Title
Third Technical Meeting on Plasma Disruptions and their Mitigation. Presentations
Imprint Pagination
vp.
Journal Page Range
26 p.
Report number
INIS-XA--24M3135

Conference

Title
3. Technical Meeting on Plasma Disruptions and their Mitigation
Dates
3-6 Sep 2024
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
55090929
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DOUBLET-3 DEVICE; ITER TOKAMAK; MAGNETOHYDRODYNAMICS; PLASMA; RELATIVISTIC RANGE; RUNAWAY ELECTRONS
Descriptors DEC
CLOSED PLASMA DEVICES; ELECTRONS; ELEMENTARY PARTICLES; ENERGY RANGE; FERMIONS; FLUID MECHANICS; HYDRODYNAMICS; LEPTONS; MECHANICS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
Imprint:Refs.