模拟放射性含硼废液的水泥固化研究  

Study on Cementation of Simulated Radioactive Borated Liquid Wastes

作　　者：孙奇娜[1,2] 李俊峰[1] 王建龙[1,3] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084 [2]中国环境管理干部学院,河北秦皇岛066004 [3]清华大学环境模拟与污染控制国家重点联合试验室,北京100084

出　　处：《原子能科学技术》2010年第B09期153-158,共6页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(20701024)

摘　　要：为了比较硫铝酸盐水泥和普通硅酸盐水泥含硼废液的固化,为配方优化提供依据,研究采用两种配方对模拟放射性含硼废液进行水泥固化。测定了固化体28d抗压强度、抗浸泡性、抗冻融性和耐γ辐照试验后的强度损失,进行了模拟核素浸出试验,并对固化体水化产物进行XRD分析。结果表明,两种配方可有效固化模拟含硼废液,固化体28d抗压强度、各项试验强度损失和模拟核素浸出率均满足GB14569.1—93的要求,试验所用的硫铝酸盐水泥配方对Cs+的滞留能力优于普通硅酸盐水泥配方,固化体中的硼以B(OH)4-形式固溶在钙矾石中。To compare sulfoaluminate cement with ordinary Portland cement on their cementation of radioactive borated liquid waste and to provide more data for formula optimization, simulated radioactive borated liquid waste were solidified by the two cements. 28 d compressive strength and strength losses after water/freezing/irradiation resistance tests were investigated. Leaching test and X-ray diffraction analysis were also conducted. The results show that it is feasible to solidify borated liquid wastes with sulfoaluminate cement and ordinary Portland cement with formulas used in the study. The 28 d compressive strengths, strength losses after tests and simulated nuclides leaching rates of the solidified waste forms meet the demand of GB 14569.1—93. The sulfoaluminate cement formula show better retention of Cs＋ than ordinary Portland cement formula. Boron, in form of B（OH）4-, incorporat in ettringite as solid solutions.

关 键 词：水泥固化 含硼废液 抗压强度 浸出试验 钙矾石 

分 类 号：TL75[核科学技术—辐射防护及环境保护] X58[环境科学与工程—环境工程]