通用水泥固化模拟放射性废树脂的可行性及机理

Feasibility and Mechanism of Solidifying Simulated Radioactive Waste Resin Using Ordinary Portland Cement

  • 摘要: 为系统研究通用水泥固化放射性废树脂的可行性,并揭示不同品牌水泥在性能上的共性与差异,在固定配比条件下,选取通用水泥B品牌PII42.5R、PO42.5R及C品牌PO42.5R与专用水泥A品牌,开展了实验室与400 L工程规模双尺度试验,结合XRD、SEM、EDS、FT-IR等微观表征与浸出试验,系统分析了固化体的物理性能、化学稳定性及工程适应性。结果表明,通用水泥固化体性能均满足GB 41930—2022要求,其中C品牌水泥在实验室与工程钻芯试块中28 d强度分别为31.54 MPa与35.18 MPa,均高于标准下限(7 MPa)。微观机理分析表明,所有通用水泥体系均形成了以水化硅酸钙(C-S-H)凝胶为主体的致密结构框架。在此框架内,模拟核素固定机制各有不同:Co2+主要通过固溶作用进入C-S-H凝胶晶格,Cs+以吸附为主,而Sr2+则主要形成化学沉淀,化学固定与基体致密化协同作用使浸出液中模拟核素浓度低于安全限值。该研究证明通用水泥能够实现放射性废树脂的有效固化,在保障长期安全的同时具有工程经济价值。

     

    Abstract: To systematically evaluate the feasibility of solidifying radioactive waste resin using ordinary Portland cement and to compare the performance commonalities and differences among various cement brands, three ordinary Portland cements (B-brand PII42.5R and PO42.5R, and C-brand PO42.5R) were selected together with a dedicated cement (A-brand PII-A) as a comparison. Under a fixed mix proportion, laboratory-scale tests were carried out for all four cements, and two optimally performing cements were further subjected to a 400 L engineering-scale cold test. Microstructural characterizations including X-ray diffraction (XRD), scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDS), and Fourier-transform infrared spectroscopy (FT-IR) were performed. Mechanical and durability tests such as compressive strength measurement, freeze-thaw cycling, gamma irradiation, impact resistance, and simulated nuclide leaching experiments were conducted to systematically assess the physical and mechanical properties, chemical stability, and engineering adaptability of the solidified waste forms. The results show that the 28 d compressive strengths of all ordinary Portland cement waste forms range from 21.92 MPa to 31.54 MPa, and the strength loss rates after durability tests meet the requirements of the Chinese national standard GB 41930-2022. Notably, the 28 d strengths of cement C-brand in laboratory specimens and engineering cored samples reach 31.54 MPa and 35.18 MPa, respectively, both well above the minimum requirement of 7 MPa. Microstructural analysis reveals that each cement system forms a dense structural framework dominated by calcium silicate hydrate (C-S-H) gel. Regarding the immobilization of simulated nuclides, Co2+ is mainly incorporated into the C-S-H lattice via isomorphous substitution to form a solid solution, Cs+ is primarily immobilized by adsorption, and Sr2+ predominantly forms SrSO4 precipitates. Simulated nuclide concentrations in the leachate are kept below the safety limits by the synergy between chemical fixation and matrix densification. Engineering-scale tests further confirm that the two selected cements (B-brand PII42.5R and C-brand PO42.5R) exhibit good durability. Their 28 d compressive strengths are 25.54 MPa and 22.66 MPa, respectively. No severe damage is observed after durability tests and impact loading, and the drilled cores validated the consistency of performance. Ordinary Portland cement, under appropriate mix design and processing conditions, can effectively solidify radioactive waste resin. Its hydration products share similar phase compositions and structural evolution patterns with those of the dedicated cement, thus offering both long-term safety and engineering economic value.

     

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