ORBIT simulations of fast ion power loads on the wall of the Divertor Tokamak Test

Gobbin, Marco; Spizzo, Gianluca

doi:10.1088/1361-6587/acd71d

ORBIT simulations of fast ion power loads on the wall of the Divertor Tokamak Test

Journal Article · 09 June 2023 · Plasma Physics and Controlled Fusion

DOI:https://doi.org/10.1088/1361-6587/acd71d· OSTI ID:2418887

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OSTI

Abstract

Neutral beam injection in tokamaks produces a population of fast ions, which interact with 3D magnetic fields in a variety of ways, often resulting in energetic particle losses in very short times to the wall. Careful design of neutral beams and active control of error fields helps to keep these losses to a minimum. Nevertheless, past experience in tokamaks in the 1980s and detailed simulations for future machines, such as International Thermonuclear Experimental Reactor, suggest that very localized fast ion losses (‘hot spots’) can be present, even if the overall losses are low. In this paper, we discuss this issue in the Divertor Tokamak Test (DTT) project, and we show that in the standard single-null full-power scenario of the DTT, fast ions produce two hot spots, corresponding approximately to the beam injection and exit toroidal angles: the former being mainly due to prompt losses/passing particles, while the latter is due to trapped ions. However, the maximum power load in these spots is of the order $\sim 63$ kW m⁻², below the tolerance of plasma-facing components of the machine.

Research Organization:: General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC)

DOE Contract Number:: FC02-04ER54698; FG02-95ER54309

OSTI ID:: 2418887

Journal Information:: Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 7 Vol. 65; ISSN 0741-3335

Publisher:: IOP Science

Country of Publication:: United States

Language:: English

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