Latest results from the FWLTB computer code: the influence of swelling and irradiation creep on the stainless steel first wall of a fusion reactor

1979 ◽  
Vol 85-86 ◽  
pp. 147-151 ◽  
Author(s):  
W. Daenner ◽  
J. Raeder
Keyword(s):  
Stainless Steel ◽  
Fusion Reactor ◽  
Computer Code ◽  
First Wall ◽  
Irradiation Creep

Doping of vanadium alloys with helium using tritium

1987 ◽  
Vol 45 ◽  
pp. 218-219
Author(s):  
D. N. Braski
Keyword(s):  
Stainless Steel ◽  
Fusion Reactor ◽  
Future Application ◽  
Vanadium Alloy ◽  
First Wall ◽  
Displacement Damage ◽  
Vanadium Alloys ◽  
Helium Concentration ◽  
Tritium Trick ◽  
Predetermined Time

Vanadium alloys are currently being evaluated for possible future application as a structural first wall for a fusion reactor. Major concerns are the displacement damage and high rates of helium production in a first wall caused by the 14 MeV neutrons from the plasma. To study the effect of helium on the microstructure and to simulate its effect in irradiation experiments, various vanadium alloys have been doped with helium using the “tritium trick” procedure.Vanadium alloy specimens were heated at 400°C in a stainless steel retort with tritium at 53 kPa (400 torr). Helium concentration was controlled by holding the specimens under these conditions for a predetermined time to allow the tritium, which is quite soluble in vanadium, to diffuse into the material and transmute to 3He. The process was stopped by reducing the pressure and increasing the temperature in the retort to 700°C. This removed the remaining tritium from the specimens and left the insoluble 3He behind in the microstructure.

Creep Comparison between Type 316 Stainless Steel and Nimonic PE-16 Used as the First Wall in a Fusion Reactor

1989 ◽  
Vol 16 (4) ◽  
pp. 498-506 ◽  
Author(s):  
M. Salvioni ◽  
M. Petilli ◽  
L. Tondinelli ◽  
G. Sacerdoti
Keyword(s):  
Stainless Steel ◽  
Fusion Reactor ◽  
First Wall ◽  
316 Stainless Steel

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.

Special Features of First-Wall Heat Transfer in Liquid-Metal Fusion Reactor Blankets

1987 ◽  
Vol 12 (1) ◽  
pp. 104-113 ◽  
Author(s):  
K. Taghavi ◽  
M. S. Tillack ◽  
H. Madarame
Keyword(s):  
Heat Transfer ◽  
Liquid Metal ◽  
Fusion Reactor ◽  
Wall Heat Transfer ◽  
First Wall
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