Hydrogen isotope separation for fusion power applications

Effect of Interstitial Hydrogen on the Mechanical and Thermal Properties of Tungsten: A First-Principles Study

“…2−4 Plasma facing materials are subjected to the bombardment of high-beam hydrogen isotopes deuterium and tritium, 5,6 which can result in a lot of defects and damage on the surface and bulk texture of tungsten materials, as well as the retention of hydrogen isotopes, 7,8 indicating that part of H impurities may be retained in the W lattice. 9 It is shown that H impurities tend to occupy the tetrahedral interstitial site (TIS) in W. In other words, when H occupies the tetrahedral interstitial site, it has the lowest energy and the most stable structure. 10−13 As first wall materials, the mechanics and thermal properties are very important for the service of materials, and high mechanical strength and high thermal conductivity are good for material applications.…”

“…First wall material for controlled thermonuclear fusion energy is one important engineering material that can bear the high-temperature and high-radiation conditions. W and its alloys are considered as the most promising first wall materials at present due to their high melting point, high thermal conductivity, high strength at high temperatures, low thermal expansion coefficient, low sputtering yield and high sputtering threshold, low vapor pressure, and low tritium retention. − Plasma facing materials are subjected to the bombardment of high-beam hydrogen isotopes deuterium and tritium, , which can result in a lot of defects and damage on the surface and bulk texture of tungsten materials, as well as the retention of hydrogen isotopes, , indicating that part of H impurities may be retained in the W lattice . It is shown that H impurities tend to occupy the tetrahedral interstitial site (TIS) in W. In other words, when H occupies the tetrahedral interstitial site, it has the lowest energy and the most stable structure. − …”

Recent progress in the experimental and theoretical studies on the barium zirconate proton conductors: A review

“…The proton-conducting oxides have a potential application in the fusion reactor's isotope separation systems [15,103,[152][153][154][155][156][157][158][159], hydrogen pump for tritium puri cation and recovery [160][161][162][163][164][165], and also as hydrogen sensors [31][32][33][34][35][36][37]and fuel cells [5][6][7][8][9][10]. Therefore, to advance in practical usage of oxide proton conductors as functional materials, it is essential to understand the hydrogen behavior in the proton-conducting materials, such as the amount of dissolution and internal diffusion of hydrogen [166][167][168][169][170].…”

The effect of pore sizes on D2/H2 separation conducted by MOF-74 analogues

“…To date, this technology has not been effectively overcome. [1][2][3][4] The extraction, separation, and purification of H 2 and D 2 are very difficult due to their almost identical sizes, shapes, and physicochemical properties. Traditional techniques, such as low-temperature distillation, thermal diffusion, centrifugation, laser separation, and chromatography, are energy-intensive, inefficient, and costly.…”