Deuterium permeation through beryllium with surface element composition control

Tazhibaeva, I. L.; Shestakov, V.; Chikhray, Y.; Romanenko, O. G.; Klepikov, A.Kh.; Saksaganskiy, G.L.; Prokofiev, Yu.G.; Mazaev, S. N.

doi:10.1016/b978-0-444-82220-8.50075-3

Cited by 9 publications

(11 citation statements)

References 3 publications

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“…The different reported diffusivities are shown in Figure 8. It can be seen that the diffusivity reported by Abramov, et al [74] is considerably larger than those of Tazhibaeva, et al [72] and Jones and Gibson [73]. It is apparent that the purity of the beryllium played a strong role in determining the effective diffusivity.…”

Section: Berylliumcontrasting

confidence: 40%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

132

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Tritium and deuterium induce radiation in reactor materials and some radioactive tritium gas may be released. Most of the materials used in fusion reactors are metals that have relatively high permeabilities for tritium. The fusion community has been working on barriers to minimize tritium release. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments.This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The necessary parameters for tritium release calculations for various regions of a fusion reactor are given.

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Section: Berylliumcontrasting

confidence: 40%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

132

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“…11͒ and 1.6-1.8 eV. 11,[27][28][29] The available experimental data on hydrogen mobility mostly evidence that hydrogen isotopes are fast diffusers in Be, with the experimental estimates for the migration energy of 0.12-0.36 eV, 23,24,[29][30][31][32] though a relatively high estimate of 0.77 eV can also be met in the literature. 33 In order to get a better understanding of hydrogen properties at the atomistic level, it is a common practice to use numerical techniques, though the simulations of defects in beryllium are still rare.…”

Section: Introductionmentioning

confidence: 94%

Hydrogen in beryllium: Solubility, transport, and trapping

2009

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The paper presents the results of ab initio simulation of hydrogen properties in beryllium. Both interstitial hydrogen positions in the lattice and various hydrogen positions in a vacancy have been studied. The most energetically favorable interstitial hydrogen configuration among the four considered high-symmetry configurations is the basal tetrahedral one, in agreement with the earlier predictions. The most probable diffusion pathway for hydrogen atoms in the bulk involves the exchange of octahedral and basal tetrahedral positions with the effective migration energy of ϳ0.4 eV. For hydrogen atom in a vacancy, an off-center ͑nearly basal tetrahedral͒ configuration is definitely preferred. Addition of more hydrogen atoms to a vacancy remains energetically favorable up to at least five hydrogen atoms, though the binding energies fall down with the increase in the number of hydrogen atoms in the vacancy.

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“…[403,430,432,433] Many studies have been done of the retention and emission of H implanted into materials to provide data needed to predict H retention in fusion reactor environments. Fig.…”

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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Deuterium permeation through beryllium with surface element composition control

Cited by 9 publications

References 3 publications

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Hydrogen in beryllium: Solubility, transport, and trapping

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

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