A mature industrial solution for ITER divertor plasma facing components: Hypervapotron cooling concept adapted to Tore Supra flat tile technology

Escourbiac, F.; Bobin-Vastra, I.; Кузнецов, В. Е.; Missirlian, M.; Schedler, B.; Schlösser, J.

doi:10.1016/j.fusengdes.2005.06.328

Cited by 32 publications

(10 citation statements)

References 5 publications

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“…However, the material limits (e.g. tungsten) imposes that divertor targets cannot sustain a heat flux higher than around 20 MW m −2 [1], which can be exceeded by an order of magnitude in a fusion reactor if no mitigation steps are taken. The lifespan of the target can also be greatly shortened not only because of erosion, but also melting if the heat flux is above 20 MW m −2 .…”

Section: Introductionmentioning

confidence: 99%

One-dimensional simulation and validation of divertor detachment induced through nitrogen seeding on HL-2A

Zhou,

Dudson,

et al. 2024

Plasma Phys. Control. Fusion

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Divertor detachment is a promising method to solve the power exhaust problem in tokamak devices or even in future magnetic fusion reactors. In this work, a detachment experiment (HL-2A shot #38008) with mixed gas seeding (60% nitrogen & 40% deuterium) is simulated using the SD1D module in BOUT++. In the process from attachment to detachment, the target electron temperature and the target ion saturation current in simulations are found to be consistent with the experimental results measured by Langmuir probes on the target plate. In order to understand the underlying detachment mechanism on HL-2A, this work analyses the role of different particle species in the cases with different seeding rates. It shows that the plasma density varies little and the density of neutrals (D and D_2) slightly decreases with the increase of nitrogen seeding rate, such that plasma-neutral interactions cannot effectively reduce plasma energy and plasma momentum in the divertor. The case with a high seeding rate predicts that increasing seeding rate cannot reach a target temperature lower than 2.5eV, which is the required temperature for strong plasma-molecule interactions. Thus, the plasma-molecule interactions may not be important in the divertor during nitrogen seeding. This work also studies the parallel forces including 1) force due to the parallel electric field, 2) friction forces, 3) ion- and electron- thermal forces, and 4) collisional reactions (e.g. charge exchange recombination (CXR) and ionisation). It is found that the friction force between nitrogen ions and other particle species (primarily D^+) is the dominant force towards the target, while ion- and electron- thermal forces are the dominant force pushing nitrogen ions back to upstream. Parallel forces determine the parallel distribution of nitrogen impurities, and therefore decide the region of nitrogen radiation.

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Section: Introductionmentioning

confidence: 99%

One-dimensional simulation and validation of divertor detachment induced through nitrogen seeding on HL-2A

Zhou,

Dudson,

et al. 2024

Plasma Phys. Control. Fusion

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“…For example, the first wall design of the ITER high thermal water-cooled shield blanket and the neutral beam injection cooling design of the JET [5]. Escourbiac [6] et al experimentally verified the feasibility of the hypervapotron structure that can be applied to the ITER water-cooled divertor scheme, carrying a maximum heat flow density of 10 MW/m 2 to 20 MW/m 2 . Khodabandeh [7] et al carried out experiments on the flow of cooling mass in a cavity and a channel with rectangular ribs.…”

Section: Introductionmentioning

confidence: 99%

Numerical Investigation on Enhanced Heat Transfer with Tilted Hypervapotron Structure of the Fusion Blanket

Gao

et al. 2023

J. Phys.: Conf. Ser.

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High flux components in fusion reactor are designed to transfer high thermal loads from the core plasma under steady-state operation and emergency conditions. In order to improve the heat transfer ability, hypervapotron structure is proposed to promote the heat transfer performance by optimizing the thermal hydraulic design. In this paper, three-dimensional numerical simulation was carried out using CFD methods for the improved solution of the first wall. The results show that the heat transfer performance of the triangular fin structure with tilt angle of 30° is superior to 0 °, 15°and 45°. At a typical flow rate of 2 m/s, the heat transfer efficiency of the triangular fin with tilt angle of 30° improved by a maximum of 118.1% compared with that of the smooth flow channel. In addition, the heat transfer performance of the triangular fin structure is better than other fin structure, and its maximum temperature drops by 136.3K compared to the smooth flow channel. The design solution may provide a viable new method for efficient cooling of future fusion reactor components with high heat flux.

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“…Nevertheless, some tiles of the qualification targets for the W7-X divertor revealed hot spots at 10 MW/m 2 after a view thermal cycles whereas other tiles of the same component have been cycled successfully even at heat fluxes exceeding 20 MW/m 2 [1]. On the other hand, flat tiles with a shear strength accounting for less than 25% compared to the W7-X targets have absorbed successfully a heat flux as high as 20 MW/m 2 [10]. These results reveal that shear test values do not appear reliable to predict the performance of a C/C armour joint.…”

Section: Introductionmentioning

confidence: 99%

Methods to determine the joint strength of C/C to copper joints

Schedler

Huber

Eidenberger

et al. 2007

Fusion Engineering and Design

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A mature industrial solution for ITER divertor plasma facing components: Hypervapotron cooling concept adapted to Tore Supra flat tile technology

Cited by 32 publications

References 5 publications

One-dimensional simulation and validation of divertor detachment induced through nitrogen seeding on HL-2A

One-dimensional simulation and validation of divertor detachment induced through nitrogen seeding on HL-2A

Numerical Investigation on Enhanced Heat Transfer with Tilted Hypervapotron Structure of the Fusion Blanket

Methods to determine the joint strength of C/C to copper joints

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