High heat flux tests on heat sinks armored with tungsten rods

Nygren, R.E.; Youchison, D.L.; Watson, R.D.; O’Dell, Scott

doi:10.1016/s0920-3796(00)00388-4

Cited by 20 publications

(14 citation statements)

References 13 publications

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“…Recently, substantial progress has also been made on the development and testing of water-cooled high heat-flux components clad with beryllium and with tungsten [250]. W-armoured prototypes already promise to be as reliable, at similar heat fluxes, as their carbon armoured counterparts [253][254][255]. This requires, particularly for materials like tungsten, the use of "discrete" structures (e.g., castellated, brush-type, etc.)…”

Section: Selection Criteria For Plasma-facing Materialsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Selection Criteria For Plasma-facing Materialsmentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…In contrast, a 10 m radius IFE chamber, such as the high average power laser (HAPL) reactor [4] is expected to be exposed to helium and deuterium ions ranging in energy from 1 keV to 10 MeV, with a low energy helium flux of about $10 15 m À2 in the range of 100-200 keV and a high energy helium flux of $10 16 m À2 between 200 keV and 10 MeV (per shot from a 365 MJ target). For both applications, tungsten is chosen as a primary candidate armor material, because of high temperature capabilities, relatively high thermal conductivities, good sputtering erosion resistance, and near zero tritium retention [5,6]. However, there is compelling experimental evidence that low and high energy helium implantation of tungsten can result in drastic changes in the surface morphology over a wide temperature range [7][8][9][10][11][12].…”

Section: Introductionmentioning

confidence: 99%

A description of stress driven bubble growth of helium implanted tungsten

Sharafat

Takahashi

Nagasawa

et al. 2009

Journal of Nuclear Materials

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“…Concerns linked with high carbon erosion rates, tritium retention at low temperatures, and radiation enhanced sublimation necessitate development of other FW armor concepts. Refractory metals, such as tungsten are an attractive option because they offer high temperature capabilities, relatively high and predictable thermal conductivities, good sputtering erosion resistance, and near zero tritium retention [3][4][5]. Allowable erosion rates are extremely stringent and limited to less than 0.02 lm per shot for a tungsten armored FW of the HAPL engineering test facility (ETF).…”

Section: Introductionmentioning

confidence: 99%