Deuterium retention and re-emission from tungsten materials

Alimov, V. Kh.; Scherzer, B.M.U.

doi:10.1016/s0022-3115(96)00442-4

Cited by 60 publications

(14 citation statements)

References 14 publications

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“…At high fluences deuterium retention in W is higher at 500 K than at 300 K [437]. Comparison between total retention measured by thermal desorption spectroscopy (TDS) and near-surface retention measured by NRA indicates that in W much of the D is retained beyond the range of implantation [426,438]. Retention of H implanted in W is due to trapping at defects and precipitation into bubbles.…”

Section: Insert Fig 29mentioning

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: Insert Fig 29mentioning

confidence: 99%

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

et al. 2001

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“…The amount of hydrogen retained and peculiarities of retention strongly depend on the material structure, which in turn depends on the material production procedure [10]. Most experiments in this field were performed with polycrystalline (PCW) or monocrystalline (SCW) tungsten, while data for plasma-sprayed tungsten (PSW) are very scarce and far from being complete.…”

Section: Introductionmentioning

confidence: 99%

“…Laboratory data on hydrogen interaction with PSW are very scarce [9,10]. The investigation in [9] was performed for ASDEX Upgrade before the first tungsten divertor campaign in order to predict the deuterium capture in plasmasprayed tungsten.…”

Section: Introductionmentioning

confidence: 99%

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Hydrogen Retention In Plasma-Sprayed Tungsten

Голубева

Kurnaev

Mayer

et al. 2006

AIP Conference Proceedings

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Abstract.Deuterium retention in plasma-sprayed tungsten (PSW) was investigated by means of the thermodesorption technique. . The observed retention in PSW is four times higher than in polycrystalline tungsten (PCW). An additional high-temperature peak was found in the thermodesorption spectra of PSW (at 1050 K). The nature of the high-temperature peak and the mechanism of higher retention in PSW are discussed.

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“…Most recent investigations [44] lead to the conclusion that the observed blistering has to be attributed to the samples themselves, since it is only observed in cold rolled W foils, which are not relevant to reactor applications. The hydrogen retention in tungsten depends on several factors, such as material grade, fabrication process, temperature and ion energy (see for example [45]). The retained D is highest for temperatures at 400-500 K and decreases strongly with increasing temperature.…”

Section: Displacement Damages Hydrogen Retention and He-bubble Formamentioning

confidence: 99%

High-Z plasma facing components in fusion devices: boundary conditions and operational experiences

Neu

2006

Phys. Scr.

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In present day fusion devices optimization of the performance and experimental freedom motivates the use of low-Z plasma facing materials. However in a future fusion reactor, for economic reasons a sufficient lifetime of the first wall components is essential. Additionally, tritium retention has to be small to meet safety requirements. Tungsten appears to be the most realistic material choice for reactor plasma facing components (PFCs) because it exhibits the lowest erosion. But besides this there are a lot of criteria which has to be fulfilled simultaineously in a reactor. Results from present day devices and from laboratory experiments confirm the advantages of high-Z PFM but also point to operational restrictions, when using them as PFCs. They are associated with the central impurity concentration, which is determined by the sputtering yield, the penetration of the impurities and their transport within the confined plasma. The restrictions could exclude successful operation of a reactor, but concomitantly there exist remedies to ameliorate their impact. Obviously some price has to be paid in terms of reduced performance but lacking of materials or concepts which could substitute high-Z PFCs, emphasis has to be put on the development and optimization of reactor relevant scenarios which incorporate the experiences and measures.

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Deuterium retention and re-emission from tungsten materials

Cited by 60 publications

References 14 publications

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

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

Hydrogen Retention In Plasma-Sprayed Tungsten

High-Z plasma facing components in fusion devices: boundary conditions and operational experiences

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