The
ceramic material Li2ZrO3 has superior
thermo-physical and thermo-chemical properties and is highly compatible
with other blanket materials used in nuclear reactors. Like LiAlO2, it could be used in the form of an annular pellet in tritium-producing
burnable absorber rods (TPBARs) to produce tritium(3H)
upon thermal neutron irradiation of lithium isotope (6Li).
The radiation damaged pellet crystal contains vacancies, defects of
its constituent elements, and several other trapping sites which hinder
the 3H diffusion process and releasing behavior. In this
study, we investigate the diffusion mechanisms of 3H and
O3H species in Li2ZrO3 ceramic pellet
in order to understand the effects on diffusion barriers and diffusion
coefficients due to the presence of interstitial and substitutional
Li defects, hydroxide (O–3H) vacancy defect, and
of the interactions of 3H with O-vacancies in the radiation
damaged Li2ZrO3 crystal. We consider several
possible diffusion pathways of interstitial and substitutional 3H and its species in a defective supercell and calculate the
activation energy barrier profiles. We find that the smallest activation
energy barrier is 0.3 eV and corresponding diffusion coefficient at
600 K is 1.93 × 10–9 m2/s for 3H substitutional diffusion. The smallest 3H interstitial
diffusion barrier and diffusion coefficient are found to be 0.34 eV
and 3.25 × 10–9 m2/s. By examining
several channels for diffusion, our results show the most likely diffusion
mechanism of 3H migration is occurring along the c-direction by exchange of 3H within and between
different Li sites. Our calculated results reveal that the smallest
energy barrier for O3H diffusion is 0.75 eV which is when
O3H is diffusing to the O–Li vacancy pair and the
corresponding diffusion coefficient is 6.31 × 10–13 m2/s. In terms of 3H diffusion, the obtained
results indicate that the performance of Li2ZrO3 could be better than γ-LiAlO2, a widely used ceramic
material in TPBAR for producing 3H.