Beryllides for fusion reactors

J Reimann,P. Kurinskiy,R. Lindau,A. Moeslang,M. Rohde,C. Dorn,W. Haws,A. Goraieb,H. Harsch,Ch. Linsmeier

Beryllides for fusion reactors

2009

J Reimann
P. Kurinskiy
R. Lindau
A. Moeslang
M. Rohde
C. Dorn
W. Haws
A. Goraieb
H. Harsch
Ch. Linsmeier

In fusion reactors, Be is a candidate material for both ceramic breeder blankets in the form of pebbles and as plasma facing components (PFC) at the First Wall in the form of tiles.

Keywords:

Ceramic
Titanium
Intermetallic
Plasma
Fusion power
Beryllide
Materials science
Composite material
Thermal conductivity
Beryllium
Breeder (animal)
Metallurgy
Blanket

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