Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti

Abstract

The present work is an attempt to obtain data concerning the influence of neutron and irradiation upon hydrogen retention in V-4Cr-4Ti vanadium alloy. The experiments on in-pile loading of vanadium alloy specimens at the neutron flux density 10 14 n/cm 2 s, hydrogen pressure of 80 Pa, and temperatures of 563, 613, and 773 K were carried out using the IVG.1M reactor of the Kazakhstan National Nuclear Center. A preliminary set of loading/degassing experiments with non-irradiated material has been carried out to obtain data on hydrogen interaction with vanadium alloy. The, data presented in this work are related both to non-irradiated and irradiated samples.

Tritium Barriers and Tritium Diffusion in Fusion Reactors

“…The two groups also each reported a deviation from exponential behavior at lower temperatures, which could be attributed to some combination of surface effects, trapping, and a V-H phase transition at ≈200 K [119]. However, deviation from Arrhenius behavior is common in BCC metals [120] and has been reported in a number of studies on V. The transition temperature from exponential behavior varies widely with the technique used to measure diffusivity and the group that measures it [118,119,[121][122][123][124][125][126], and has been as high as 813 K when measuring uncharged specimens using the absorption technique [121]. This supports the notion that much of the deviation reported in the literature may be due to surface recombination limitation at lower temperature.…”

“…Figure 15. Solubility of hydrogen in V and its alloys [123,197,[230][231][232][233]. The bold line represents the relationship for pure V, reported in Ref.…”

Dissolution, diffusion and permeation behavior of hydrogen in vanadium: a first-principles investigation

“…In a fusion reactor, the retention and the permeation of H isotopes are some of the most important issues. In particular, tritium (T) retention and permeation of the reactor system are of great safety concern [16][17][18]. Experimentally, the retention, diffusion, and permeation properties of H isotopes in intrinsic V or V alloys have been investigated [16][17][18][19][20][21].…”