Hydrogen Adsorption Behavior on Stainless Steel for Cooling Pipe in Fusion Reactor

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S. Tanaka ◽  
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S.N. Ghali ◽  
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Author(s):  
D. N. Braski

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.


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