Effect of Ti substitution on hydrogen storage properties of Zr1−xTixCo (x = 0, 0.1, 0.2, 0.3) alloys

Structural and Kinetic Hydrogen Sorption Properties of Zr0.8Ti0.2Co Alloy Prepared by Ball Milling

“…Figure 1 represents the XRD patterns of activated Zr 0.8 Ti 0.2 Co samples after ball milling for different time. It can be found that Zr 0.8 Ti 0.2 Co samples still keep ZrCo phase except for trace amount of ZrCo 2 phase, which is identical with previous researches [ 26 , 27 ]. Meanwhile, it is clear that the intensities of ZrCo diffraction peaks decrease and the peaks exhibit broadened characteristics with increasing ball milling time.…”

“…In the meantime, hydrogen sorption cycles do not produce separated ZrCo, TiCo, and ZrH 2 , suggesting that the antidisproportionation property of ZrCo alloy is improved by Ti substitution. Zhao et al also confirmed that partial substitution of Ti for Zr will significantly enhance the antidisproportionation property of ZrCo [ 26 , 27 ]. Zhang et al [ 28 ] systematically compared the effects of Ti substitution on the disproportionation behaviors of ZrCo with Sc, Ni, and Fe elements.…”

“…Although it seems that Ti-substituted ZrCo alloy possesses the improved antidisproportionation property, the requirements of practical application still cannot be completely satisfied due to its stagnant hydrogen sorption kinetics. Zhao et al [ 26 ] reported that the hydrogen absorption amount and rate of ZrCo decrease with the Ti content increasing. Moreover, Shmayda et al [ 31 ] and Yoo et al [ 32 ] showed that the kinetic response of ZrCo for hydrogen sorption is slower than uranium, which restricts the application of ZrCo alloy.…”

Research Progress on the Anti-Disproportionation of the ZrCo Alloy by Element Substitution

“…In the study of its principle, it was found that Ti substitution reduces the hydrogen occupation of the 8e site and increases the corresponding Zr–H distance [ 48 ]. The lattice parameters and cell volume also decrease as the Ti content increases, as shown in Table 1 [ 9 , 72 , 73 , 74 ].…”

Effects of temperature and hydrogen pressure on the activation behavior of ZrCo

“…Compared with DU, ZrCo possesses such desirable properties as non-radioactivation, low pyrophoricity and small volume expansion during the hydrogen recovery/delivery cycles [11e14]. Moreover, the temperature of ZrCo needed to reach equilibrium pressure of 1 bar is much lower than that of DU, which is beneficial to minimal permeation loss of tritium and heat radiation damage [15]. In view of these, ZrCo has attracted considerable interests from the ITER team as an important alternative material for deuterium-tritium gases storage [16].…”