Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor

Nicholas, Jack R.; Ireland, Peter T.; Hancock, David; Robertson, D.

doi:10.1016/j.fusengdes.2015.03.033

Cited by 4 publications

(5 citation statements)

References 9 publications

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“…It was hence always an option to further develop the so-called flat-tile approaches for use in future devices. Among these approaches are recent developments utilizing flat tungsten armor [30][31][32][33][34] similar to the ones discussed here. Critical for all of these approaches is the viability of the material choices and the joints.…”

Section: Flat-tile Design Optionsmentioning

confidence: 99%

Evolution of Tungsten Fiber‐Reinforced Tungsten‐Remarks on Production and Joining

et al. 2023

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Material issues pose a significant challenge for the design of future fusion reactors. These issues require new advanced materials to be developed. W‐fiber‐reinforced W‐composite material (W f/W) incorporates extrinsic toughening mechanisms increasing the resistance against failure and thus granting steps toward application in a future fusion reactor. W f/W can be produced based on chemical vapor deposition or powder metallurgical routes. In this contribution, the efforts of upscaling the production of W f/W will be reviewed based on recent results. In addition, the activities related to enabling large‐scale production for new fusion applications are being studied. Herein, two main achievements are to be highlighted. First, an upscaled production is established to produce flat tile samples for joining tests on copper and steel, and second, a new method of joining W f/W on copper is established and tested under high heat‐flux conditions.

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Section: Flat-tile Design Optionsmentioning

confidence: 99%

Evolution of Tungsten Fiber‐Reinforced Tungsten‐Remarks on Production and Joining

et al. 2023

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“…However, the value for η P is typically significantly lower when water is used as the coolant. For example, the ITER-like Monoblock concept has a pumping ratio of 0.0049 [22]. Therefore, this water-cooled design must meet or exceed the hydraulic performance of the ITER-like design.…”

Section: D Numerical Optimizationmentioning

confidence: 99%

“…The wall overheat, τ s , was then defined using the maximum heat sink temperature and the coolant inlet temperature, T ci [22]. For a specific dimensionless mass flow (m * ), an efficient cooling system will minimize τ s…”

Section: D Numerical Optimizationmentioning

confidence: 99%

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Development of a Novel DEMO divertor target: spiral plate module

et al. 2021

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In DEMO, the divertor must endure steady state loads of 10 MW m−2 and transient thermal cycling up to 20 MW m−2. A novel divertor target, termed the Spiral Plate Module (SPM) and designed to meet these loads, was initially optimized by a one-dimensional, steady-state model. The best design was a trade-off between the wall overheat (τ s )—a figure of merit for cooling performanceand the pumping ratio (η P )—a comparison of the pressure drop and the incident heat flux on a target surface. A three-dimensional, steady-state, conjugate heat transfer study showed significant correlation to the one-dimensional model. Compared to other divertor target concepts, the SPM achieved the lowest wall overheat of any target design. The hydraulic performance was also on par with comparable designs, demonstrating a very low pumping ratio. This novel, modular divertor target could be used in future fusion power plants to effectively cool the plasma facing components with low pressure drop.

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“…A third, high pressure cascade jet impingement concept [11] draws on elements of both of these with a focus on thermal efficiency as well as high performance, but has yet to be fully tested in a representative environment or a manufacturing route proven.…”

Section: Figure 1: Iter-like and Helium Cooled Divertor Target Designsmentioning

confidence: 99%

Refractory metals as structural materials for fusion high heat flux components

Hancock

Homfray

Porton

et al. 2018

Journal of Nuclear Materials

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Tungsten is the favoured armour material for plasma facing components for future fusion reactors, but studies examining the use of tungsten or other refractory metals in the underlying cooled structures have historically excluded them, leaving current concepts heavily dependent on copper alloys such as copper chrome zirconium. This paper first outlines the challenge of selecting an appropriate alternative material for this application, with reference to historical selection methodology and design solutions, and then reexamines the use of refractory metals in the light of current design priorities and manufacturing techniques. The rationale for considering refractory alloys as structural materials is discussed, showing how this is the result of relatively small changes to the logic previously applied, with a greater emphasis on high temperature operation, a re-evaluation of current costs, a relaxation of absolute activation limits, and the availability of advanced manufacturing techniques such as additive manufacturing. A set of qualitative and quantitative assessment criteria are proposed, drawing on the requirements detailed in the first section; including thermal and mechanical performance, radiation damage tolerance, manufacturability, and cost and availability. Considering these criteria in parallel rather than sequence gives a less binary approach to material selection and instead provides a strengths and weaknesses based summary from which more nuanced conclusions can be drawn. Data on relevant material properties for a range of candidate materials, including elemental refractory metals and a selection of related alloys are gathered from a range of sources and collated using a newly developed set of tools written in the python language. These tools are then used to apply the aforementioned assessment criteria and display the results. The lack of relevant data for a number of promising materials is highlighted, and although a conclusive best material cannot be identified, refractory alloys in general are proposed as worthy of further investigation.

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Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor

Cited by 4 publications

References 9 publications

Evolution of Tungsten Fiber‐Reinforced Tungsten‐Remarks on Production and Joining

Evolution of Tungsten Fiber‐Reinforced Tungsten‐Remarks on Production and Joining

Development of a Novel DEMO divertor target: spiral plate module

Refractory metals as structural materials for fusion high heat flux components

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