Speaker
Description
Shurui Shang1,2, Qiang Qi1,2*, Shouxi Gu1, Hai-Shan Zhou1,2, Guang-Nan Luo1,2
1Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences, Hefei, 230031, China
2Science Island Branch, Graduate School of USTC, Hefei, 230036, China
Lithium-based ceramic tritium breeders serve as critical components in fusion blanket systems. Under neutron irradiation conditions, neutron-induced transmutation reactions that produce tritium (³H) simultaneously generate helium-4 (⁴He) atoms in a 1:1 stoichiometric ratio. Owing to its characteristically low solubility in ceramic matrices, helium readily interacts with irradiation-induced vacancies. This interaction may drive void nucleation, followed by helium accumulation within these voids to form helium bubbles. Critically, such defects induced by helium behavior may act as trapping sites for tritium, thereby altering its release dynamics.The changes of phase, microstructure, chemical states and its effects on release behavior of hydrogen isotopes in helium and deuterium irradiated Li2TiO3 have been investigated. SRIM-2013 simulations revealed that 100 keV helium (He) ion irradiation induced lattice defects distributed up to 500 nm beneath the surface, with a peak damage level of 2.7 displacements per atom (DPA). Following helium ion irradiation, the characteristic Ti2p peaks at 458.2 eV and 464.0 eV were quenched. Following 50 keV deuterium (D) ion irradiation, the helium-containing microstructure of Li₂TiO₃ was characterized by transmission electron microscopy (TEM), while the deuterium release kinetics were analyzed via thermal desorption spectroscopy (TDS).
