Fusion Science and Technology / Volume 60 / Number 4 / November 2011 / Pages 1580-1583
Interaction with Materials / Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) / dx.doi.org/10.13182/FST11-A12736
Tensile and creep strength of pure V, Nb, Ta, and Nb-9W alloy were examined at 600 °C to assess their applicability as hydrogen permeation material for the recovery of tritium from the high temperature liquid breeder blanket of a fusion reactor. The Nb-9W alloy required a comparatively higher annealing temperature to achieve good ductility. Based on tensile strength results, it is estimated that a permeation wall thickness of 0.1 mm is achievable. According to creep rate of Nb-9W alloy, design stress maybe decreased below 1/3 of yield stress.