Implantation, Retention and Release of Hydrogen Isotopes in Solids

Moeller, W.; Post, D.; Roth, J.; Behrisch, R.

doi:10.1007/978-1-4757-0067-1_11

Cited by 13 publications

(9 citation statements)

References 87 publications

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“…This in turn impacts particle and energy confinement (Sect. 1.2.3) [374][375][376][377]. Tritium inventory and permeation of tritium through the wall or into coolant channels are also concerns for reactors.…”

Section: Hydrogen Interactions With 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: Hydrogen Interactions With 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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“…According to the diffusion-trapping theory of H retention in metals, at high temperatures the equilibrium fractional occupancy of a particular trapping site is a result of the competition between H trapping and detrapping processes. Consequently, at a given temperature it increases with increasing H binding energy to the trapping site and the local concentration of solute H [30][31][32]. During plasma exposure the local steady-state concentration of solute H is proportional to the non-reflected part of the incident ion flux, if the H release is not surface-limited.…”

Section: Discussionmentioning

confidence: 99%

The high-flux effect on deuterium retention in TiC and TaC doped tungsten at high temperatures

Zibrov

Bystrov

Mayer

et al. 2017

Journal of Nuclear Materials

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Samples made of tungsten (W) doped either with titanium carbide (W-1.1TiC) or tantalum carbide (W-3.3TaC) were exposed to a low-energy (40 eV/D), high-flux (1.8-5×10 23 D/m 2 s) deuterium (D) plasma at temperatures of about 800 K, 1050 K, and 1250 K to a fluence of about 1×10 27 D/m 2. The deuterium (D) inventory in the samples was examined by nuclear reaction analysis and thermal desorption spectroscopy. At 800 K the D bulk concentrations and total D inventories in W-1.1TiC and W-3.3TaC were more than one order of magnitude higher compared to that in pure polycrystalline W. At 1050 K and 1250 K the D concentrations in all types of samples were very low (≤10 5 at. fr.); however the D inventories in W-1.1TiC were significantly higher compared to those in W-3.3TaC and pure W. It is suggested that D trapping inside the carbide precipitates and at their boundaries is essential at high temperatures and high incident fluxes, especially in W-1.1TiC.

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“…Using Eq. (1) and the diffusivity data for stainless steel [13], the diffusion distances have been estimated to be 1.9 mm for F82H and 0.019 mm for SUS304 in 900 s at 290 • C, which can explain their different permeation behavior shown in Fig. 3.…”

Section: Pdp Through F82h and Sus304 Membranes In Questmentioning

confidence: 91%

First Wall Particle Flux Measurements by an F82H Permeation Probe in QUEST

Zhou

Hirooka

Zushi

et al. 2014

Plasma and Fusion Research

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First wall particle flux measurements in the QUEST spherical tokamak have been conducted, using a permeation probe that employs a first wall candidate ferritic steel alloy F82H as the membrane and also SUS304 as a comparative reference membrane. Permeation measurements have been done during the conditioning steadystate discharges heated with 2.45 GHz and 8.2 GHz ECR. Diffusion and recombination coefficients measured in a laboratory-scale plasma device: VEHICLE-1 are used to interpret the results from the permeation probe measurements in QUEST. These permeation membranes have been analyzed with XPS to evaluate the effects of surface impurities.

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Implantation, Retention and Release of Hydrogen Isotopes in Solids

Cited by 13 publications

References 87 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

The high-flux effect on deuterium retention in TiC and TaC doped tungsten at high temperatures

First Wall Particle Flux Measurements by an F82H Permeation Probe in QUEST

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