摘要
The ZrCo alloy stands out as one of the most promising candidates for hydrogen isotope storage materials in nuclear fusion, owing to its extremely low equilibrium hydrogen pressure (10 −3 Pa, 20 ℃). However, ZrCo experiences severe disproportionation reactions during dehydrogenation/hydrogenation processes, which lead to significant performance degradation. To address this, we have introduced V and Ti into the ZrCo alloy, resulting in the Zr 0.8 V x Ti 0.2-x Co (x = 0–0.15) series. Our research indicates that the addition of V and Ti reduces the lattice parameters, thereby increasing the platform pressure for hydrogen desorption and decreasing the enthalpy and entropy of the desorption reaction. This modification allows for a lower desorption temperature and enhances the alloy's resistance to hydrogen-induced degradation. Remarkably, the hydrogen storage capacity of the Zr 0.8 V x Ti 0.2-x Co(x = 0–0.15) alloys remains stable after 19 h of desorption. Furthermore, the Zr 0.8 V 0.05 Ti 0.15 Co alloy demonstrates exceptional cycling stability, retaining over 99 % of its hydrogen storage capacity after 50 cycles. First-principles calculations have clarified the adsorption energies of hydrogen at different binding sites, revealing the following order of stability: E b(Ti-V) < E b(Zr-Ti) < E b(V-Zr) < E b(Zr-Zr) . The hydrogen absorption and desorption kinetics of the Zr 0.8 V x Ti 0.2-x Co alloys follow the trend: Zr 0.8 V 0.15 Ti 0.05 Co > Zr 0.8 V 0.1 Ti 0.1 Co > Zr 0.8 V 0.05 Ti 0.15 Co > ZrCo, indicating optimized performance with the introduction of V and Ti. This study not only provides a viable solution to the disproportionation issue in ZrCo alloys but also offers valuable insights into the design of high-performance hydrogen isotope storage materials for nuclear fusion applications.
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