Beryllium application in ITER plasma facing components

A.R. Raffray; G. Federici; V. Barabash; H.D. Pacher; H.‐W. Bartels; A. Cardella; R. Jakeman; K. Ioki; G. Janeschitz; R.R. Parker; R. Tivey; C.H. Wu

doi:10.1016/s0920-3796(97)00052-5

JOURNAL ARTICLE

Beryllium application in ITER plasma facing components

A.R. Raffray G. Federici V. Barabash H.D. Pacher H.‐W. Bartels A. Cardella R. Jakeman K. Ioki G. Janeschitz R.R. Parker R. Tivey C.H. Wu

Year: 1997 Journal: Fusion Engineering and Design Vol: 37 (2)Pages: 261-286 Publisher: Elsevier BV

DOI: 10.1016/s0920-3796(97)00052-5

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Keywords:

Armour Divertor Beryllium Nuclear engineering Thermonuclear fusion Limiter Tokamak Materials science Fusion power Plasma Baffle Environmental science Computer science Mechanical engineering Nuclear physics Composite material Engineering Physics

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Topics

Fusion materials and technologies

Physical Sciences → Materials Science → Materials Chemistry

Nuclear Materials and Properties

Physical Sciences → Materials Science → Materials Chemistry

Advanced materials and composites

Physical Sciences → Engineering → Mechanical Engineering

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