Design study of a tritium transport package for future fusion reactors

1999 ◽  
Vol 45 (2) ◽  
pp. 187-195 ◽  
Author(s):  
S. O’hira ◽  
T. Suzuki ◽  
S. Hode ◽  
M. Nishi
Keyword(s):  
Fusion Reactors ◽  
Design Study ◽  
Tritium Transport

Limitations on Tritium Transport through Fusion Reactors

1978 ◽  
Vol 39 (3) ◽  
pp. 258-265 ◽  
Author(s):  
Andrew S. Zarchy ◽  
Robert C. Axtmann
Keyword(s):  
Fusion Reactors ◽  
Tritium Transport

Alignment of small He-Bubbles during in situ deformation of Al-foils

1978 ◽  
Vol 36 (1) ◽  
pp. 396-397
Author(s):  
E. Ruedl ◽  
P. Schiller
Keyword(s):  
Fusion Reactor ◽  
Matrix Material ◽  
Fusion Reactors ◽  
First Wall ◽  
Potential Matrix ◽  
In Situ Deformation ◽  
Α Particles ◽  
Metal Aluminium

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.

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