Permeation of deuterium implanted into V-15Cr-5Ti

Anderl, R.A.; Longhurst, G.R.; Struttmann, D.A.

doi:10.1016/0022-3115(87)90357-6

Cited by 10 publications

(6 citation statements)

References 11 publications

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“…There are numerous publications citing instances where the codes and fit parameters have been used to simulate experiments. References [880,894,906,909,[914][915][916][917][918][919][920][921][922] are representative. Experiments have been performed and modelled on a wide range of potential plasma facing materials including Be [880, 907-909, 917, 918], C [914], Cu [456,915], stainless steel [906], V alloy [915], and W [915,[920][921][922].…”

Section: Status Of Model Validationmentioning

confidence: 99%

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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: Status Of Model Validationmentioning

confidence: 99%

“…There are numerous publications citing instances where the codes and fit parameters have been used to simulate experiments. References [875,889,901,904,[909][910][911][912][913][914][915][916][917] are representative.…”

Section: Status Of Model Validationmentioning

confidence: 99%

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

et al. 2001

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“…Because of this and the high diffusivity of tritium, release is recombination-limited in V alloys. Deuterium ion-driven permeation experiments of V-15Cr-5Ti have estimated the recombination rate coefficient to be 2.4x10 -29 m 4 s -1 [133] (although this measurement is differs by three orders of magnitude lower than measurements on more dilute alloys [134] and two orders of magnitude higher than measured in pure V [135]). It should be noted that most measured recombination rates are lower bounds due to surface oxides.…”

Section: < Figure 15 Here>mentioning

confidence: 97%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

129

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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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“…We note from the data presented in Table 6.2 and Figures 6.2 and 6.3 that nearly all of the experimental data that concern alloy element affects are derived from experiments for which specimen temperatures are quite low (e480K). One exception is the single experiment by Anderl 1987 who observed a significant reduction in deuterium diffusivity for the more complex V15Cr5Ti alloy developed for fusion materials applications. Systematic studies to determine the quantitative influence of substitutional alloy elements on hydrogen diffusivity for specimen temperatures greater than 480K are needed for fusion applications.…”

Section: Diffusivity In Vanadium Alloysmentioning

confidence: 99%

Permeation of deuterium implanted into V-15Cr-5Ti

Cited by 10 publications

References 11 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

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Assessment of database for interaction of tritium with ITER plasma facing materials

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