Synthesis of the chemically durable glass-ceramic matrix for radioactive waste immobilisation

Matrices for radioactive waste immobilization: a review

“…The normalized leach rates of Na, B, Al, Si, Nd, Ti, and Nb were obtained as 6.8 × 10 −3 , 3.7 × 10 −4 , 1.5 × 10 −2 , 2.2 × 10 −3 , 3.0 × 10 −5 , 5.1 × 10 −5 , and 5.5 × 10 −6 g m −2 day −1 after 28 days, respectively. The borosilicate glass-ceramics were synthesized with the loading of the strontium oxide content in the range of 10-25 mol% (Pilania et al, 2023). The normalized leach rates of Si, B, and Sr were obtained as 1.2 × 10 −8 , 3.7 × 10 −9 , and 1 × 10 −8 g m −2 day −1 after 30 days, respectively.…”

Co‐immobilization of a PuO2 surrogate and contaminated stainless steel within a zirconolite matrix

“…6,7 Several categories of matrices have been developed for the immobilization of high-level radioactive waste, including glass, ceramics, and glass-ceramic composites. [8][9][10][11][12][13][14] Among these, zirconolite (ideally CaZrTi 2 O 7 15 ) is considered an attractive wasteform for actinides on the basis of high waste loading, compositional flexibility, exceptional leaching durability, and radiation tolerance. 10,[16][17][18] Zirconolite is described as an anion-deficient fluoritederived superstructure and can be classified into five polytypes based on the stacking sequence of adjacent hexagonal tungsten bronze (HTB) planes and CaO 8 /ZrO 7 planes parallel to the crystallographic (0 0 1) plane within the unit cell.…”

“…Several categories of matrices have been developed for the immobilization of high‐level radioactive waste, including glass, ceramics, and glass–ceramic composites 8–14 . Among these, zirconolite (ideally CaZrTi 2 O 7 15 ) is considered an attractive wasteform for actinides on the basis of high waste loading, compositional flexibility, exceptional leaching durability, and radiation tolerance 10,16–18 .…”