LI Xiuying 1, TAO Xinyue 1, XIAO Zhuohao 1, KONG Lingbing 2, LIU Yalun 1, ZENG Xiaoling 1, YANG Ke 1, SHI Jijun 1
(1. School of Material Science and Engineering, Jingdezhen Ceramic Institute, Jingdezhen 333403, Jiangxi, China; 2. College of New Materials and New Energies, Shenzhen Technology University, Shenzhen 518118, Guangdong, China)
Abstract: Based on iron phosphate wasteform (38waste-17Fe2O3-45P2O5, in mol%, S1), six glassy wasteforms loaded with 30.6-34.7wt.% simulated high level nuclear waste (HLW) were prepared by replacing 2mol% Fe2O3 in S1 with PbO(S2), Cr2O3(S3), La2O3(S4), CeO2(S5), Bi2O3(S6) and B2O3(S7). The influences of the substitutions on structure and property of the wasteforms were studied. IR, XRD, DSC, TEC were used to examine their structure and thermal stability. Chemical durability was characterized according to their dissolution rates in 6 M HCl solution (DRAcid) and deionized water at 90 °C (DRWater). The substitutions of 2mol% Fe2O3 in S1 with B2O3(S7) and especially La2O3(S4) significantly improved chemical durability and thermal stability of the wasteforms. Chemical durability and thermal stability of S4 and S7 are superior over or comparable with those of 40Fe2O3-60P2O5 glass (F40), respectively. The dissolution rates of all the wasteforms are equal to or less than those of most borosilicate glass based vitrified nuclear wasteforms. Waste capacities of all wasteforms are higher than those reported previously.
Key words: waste immobilization; chemical durability; thermal stability; structure