Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 60 / Number 4 / Pages 1580-1583
Takuya Nagasaka, Takeo Muroga, Akio Sagara, Hiroshi Yukawa, Tomonori Nambu
Fusion Science and Technology / Volume 60 / Number 4 / Pages 1580-1583
Format:electronic copy (download)
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.
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