Beryllium as a Plasma-Facing Material for Near-Term Fusion Devices

Federici, G.; Doerner, R. P.; Lorenzetto, P.; Barabash, V.

doi:10.1016/b978-0-08-056033-5.00121-x

Cited by 19 publications

(11 citation statements)

References 147 publications

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“…by the TRIM code [3], are often used as the reference when comparing with experimental findings. While measurements of the Be sputtering yield by the hydrogen isotopes in low-flux ion beam facilities are in good agreement with TRIM [2], values measured in the high-flux linear plasma device PISCES-B are persistently by about one order of magnitude lower than the TRIM predictions [4]. This discrepancy was explained by the evolving surface morphology and the protective role of hydrogen incorporated in the Be surface [5].…”

Section: Introductionmentioning

confidence: 61%

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Erosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities

et al. 2014

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The impact of argon as a seeded plasma impurity on the plasma-material interaction properties of beryllium was studied in the PISCES-B linear plasma device. When exposed to pure deuterium plasma, the surface of beryllium forms a fine-scale grass-like structure and contains a significant fraction of deuterium, leading to the reduction of the sputtering yield.An argon fraction in plasma of 10% prevents the formation of rough surface and reduces the deuterium retention in the beryllium target by >50%. Consequently, the beryllium sputtering yield in the presence of argon remains at a level close to the prediction by the binary collision code TRIM. The total retention of deuterium in co-deposited layers remains at a similar level when argon is added, since a higher amount of deposited Be is compensated by a lower D/Be value. Aluminium also forms a fine-scale surface structure and displays a reduction of the effective sputtering yield when exposed to pure deuterium plasma and can therefore be considered as a non-toxic proxy for studying selected plasma-material interaction properties of beryllium.

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Section: Introductionmentioning

confidence: 61%

“…Because of the toxicity of beryllium, the experimental database on its plasma-material interaction (PMI) 2 properties is, however, fairly limited. An overview on beryllium as plasma-facing material is given in [2].…”

Section: Introductionmentioning

confidence: 99%

Erosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities

et al. 2014

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“…Beryllium (Be) has been on the candidate list as a PFM since the late 1980s. With the decision to use Be as the material for the ITER FW, research on its conditions and aspects most relevant to fusion has accelerated [ 36 , 37 ].…”

Section: Plasma Facing Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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“…Moreover, the ITER divertor surface is expected to be covered by a thin beryllium layer [111]. Under the appropriate plasma conditions (so that significant concentrations of beryllium remain locally deposited) and surface temperatures (so that element inter-diffusion is significant) beryllium-tungsten alloys can form, for instance Be 2 W with T m ∼ 2520 K or Be 12 W with T m ∼ 1780 K [111,[116][117][118]. As exhibited by the much lower melting points, mixed beryllium-tungsten materials are characterized by thermophysical properties that strongly depend on the alloy stoichiometry.…”

Section: A Complications In Burning Fusion Plasma Environmentsmentioning

confidence: 99%

Analytical expressions for thermophysical properties of solid and liquid tungsten relevant for fusion applications

Tolias,

Team

2017

Preprint

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The status of the literature is reviewed for several thermophysical properties of pure solid and liquid tungsten which constitute input for the modelling of intense plasma-surface interaction phenomena that are important for fusion applications. Reliable experimental data are analyzed for the latent heat of fusion, the electrical resistivity, the specific isobaric heat capacity, the thermal conductivity and the mass density from the room temperature up to the boiling point of tungsten as well as for the surface tension and the dynamic viscosity across the liquid state. Analytical expressions of high accuracy are recommended for these thermophysical properties that involved a minimum degree of extrapolations. In particular, extrapolations were only required for the surface tension and viscosity.

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Beryllium as a Plasma-Facing Material for Near-Term Fusion Devices

Cited by 19 publications

References 147 publications

Erosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities

Erosion, formation of deposited layers and fuel retention for beryllium under the influence of plasma impurities

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Analytical expressions for thermophysical properties of solid and liquid tungsten relevant for fusion applications

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