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R. A. Strehlow, H. C. Savage
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 127-137
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16282
Articles are hosted by Taylor and Francis Online.
The permeation and the pressure dependence of the permeation of hydrogen isotopes through metals and oxidized metals were studied at temperatures from 300 to 800°C and at pressures of 10-3 Torr to 1 atm. Such knowledge is important to tritium management in both fusion and fission nuclear reactors. An adequate basis for predicting the permeation of hydrogen at very low pressures has not previously been established; therefore, the two complementary objectives of this study were (a) to determine the pressure dependence of hydrogen permeation through materials of which steam generators might be built, and (b) to determine whether an oxide film might serve as a tritium permeation barrier. The metals studied included nickel, Type-304 L stainless steel, Hastelloy N, Incoloy 800, Croloy T9, Croloy T22, and Type-406 stainless steel. Deuterium, rather than normal hydrogen, was used as the permeating gas in order to achieve high sensitivity in the mass spectrometric analyses. At a given temperature, the permeation rate of deuterium through metals that are substantially free of oxide films was found to proceed with a half-power pressure dependence in accordance with the relationship
where J is the permeation flow rate, K is a constant, and P1 and P2 are the upstream and downstream gas pressures, respectively.