Jeon Ji-Hun, Lee Jong-Hwan, Lee Woo-Chun, Lee Sang-Woo, Kim Soon-Oh
Department of Geology and Research Institute of Natural Science (RINS), Gyeongsang National University (GNU), Jinju 52828, Republic of Korea.
HS Environmental Technology Research Center, Hosung Inc., Jinju 52818, Republic of Korea.
Materials (Basel). 2023 Sep 28;16(19):6462. doi: 10.3390/ma16196462.
The decommissioning process of nuclear power facilities renders hundreds of thousands of tons of various types of waste. Of these different waste types, the amount of concrete waste (CW) varies greatly depending on the type of facility, operating history, and regulation standards. From the previous decommissioning projects, CW was estimated to comprise 60-80 wt.% of the total weight of radioactive wastes. This represents a significant technical challenge to any decommissioning project. Furthermore, the disposal costs for the generated concrete wastes are a substantial part of the total budget for any decommissioning project. Thus, the development of technologies effective for the reduction and recycling of CW has become an urgent agenda globally. Blast furnace slag (BFS) is an industrial byproduct containing a sufficient amount (higher than 30%) of CaO and it can be used as a substitute for ordinary Portland cement (OPC). However, there have been few studies on the application of BFS for the treatment of radioactive waste from decommissioning processes. This study was conducted to evaluate the performance of the solidification agent using ground granulated BFS (SABFS) to pack radioactive wastes, such as the coarse aggregates of CW (CACW), waste soil (WS), and metal waste (MW). The analytical results indicated that the CaO content of the ground granulated BFS was 36.8% and it was confirmed that calcium silicate hydrate (CSH) could be activated as the precursor of the hydration reactions. In addition, the optimum water-to-binder ratio was determined to be 0.25 and Ca(OH) and CaSO were found to be the most effective alkaline and sulfate activators for improving the compressive strength of the SABFS. The maximum packing capacities of the SABFS were determined to be 9 and 13 wt.% for WC and WM, respectively, when the content of CW was fixed at 50 wt.%. The results of the leaching tests using SABFS containing radioactive wastes contaminated with Co, Cs, and Sr indicated that their leachability indices met the acceptance level for disposal. Consequently, the SABFS can be used as a solidifying agent for the safe disposal of radioactive waste.
核电设施退役过程会产生数十万吨各类废物。在这些不同类型的废物中,混凝土废物(CW)的数量因设施类型、运行历史和监管标准的不同而有很大差异。从以往的退役项目来看,混凝土废物估计占放射性废物总重量的60 - 80 wt.%。这对任何退役项目来说都是一项重大的技术挑战。此外,产生的混凝土废物的处置成本是任何退役项目总预算的重要组成部分。因此,开发有效减少和回收混凝土废物的技术已成为全球紧迫的议程。高炉矿渣(BFS)是一种工业副产品,含有足够量(高于30%)的CaO,可作为普通硅酸盐水泥(OPC)的替代品。然而,关于高炉矿渣用于处理退役过程中放射性废物的研究很少。本研究旨在评估使用磨细粒化高炉矿渣(SABFS)作为固化剂来包装放射性废物的性能,这些放射性废物包括混凝土废物粗骨料(CACW)、废土(WS)和金属废物(MW)。分析结果表明,磨细粒化高炉矿渣的CaO含量为36.8%,并且确认硅酸钙水化物(CSH)可作为水化反应的前体被激活。此外,确定最佳水胶比为0.25,发现Ca(OH)和CaSO是提高SABFS抗压强度最有效的碱性和硫酸盐活化剂。当混凝土废物含量固定为50 wt.%时,SABFS对WC和WM的最大填充容量分别确定为9 wt.%和13 wt.%。使用含有被Co、Cs和Sr污染放射性废物的SABFS进行浸出试验的结果表明,它们的浸出指数符合处置的验收标准。因此,SABFS可作为放射性废物安全处置的固化剂。