期刊文献+

温度对含模拟α-高放核废液的磷酸镁水泥固化体性能的影响 被引量:4

Effects of Temperature on the Properties ofα-High-level Radioactive Waste Immobilized,Hardened Magnesium Phosphate Cement
下载PDF
导出
摘要 利用磷酸镁水泥(Magnesium potassium phosphate cement,MPC)对模拟α-高放核废液(HLW)进行固化,研究温度对固化体力学性能、物相组成、微观形貌及核素Cs^+浸出率的影响。BET、XRD、SEM及AAS等测试结果表明,室温下MgO、KH2PO4与高放核废液反应形成致密结构;随着温度的升高,固化体脱水,400℃时孔道结构增多,平均孔径增大,抗压强度降低,Cs^+浸出率增加;温度继续升高,磷酸镁水泥烧结陶瓷化,平均孔径逐渐减小,抗压强度增大;900℃时固化体表现出良好的陶瓷结构特征,晶粒完全熔融,晶粒间没有明显界线,Cs^+的28d浸出率为7.21×10^(-6) g/(cm^2·d)。不同温度下高放核废液的磷酸镁水泥固化体核素Cs^+的浸出率均能达到玻璃固化体的性能要求,表明磷酸镁水泥用于固化高放核废液具有明显优势。 The magnesium potassium phosphate cement(MPC)were used for immobilization of liquid acidicα-high-level radioactive waste(HLW).This work focused on the impact of heat-treatment temperature on mechanical property,phase,microstructure and Cs+leaching rate of the solidified MPC.BET,XRD,SEM and AAS results showed that the ambient temperature reaction of MgO,KH 2PO 4 and HLW could form a dense structure,several kinds of phosphate was interspersed in the structure.The solidified MPC dehydrated with the increase of heat-treatment temperature,and obtained more pore structure,large average pore size,lower compressive strength and high Cs+leaching rate after sintering at 400℃.As the temperature continued to rise,the solidified MPC was sintered and formed ceramic while the average pore diameter decreased and the compressive strength increased.The solidified MPC turned into ceramic structure after sintering at 900℃.Crystal grains melt down completely.The 28 d leaching rate of Cs+in the solidified MPC was 7.21×10-6 g/(cm 2·d).The leaching rate of Cs+could reach the performance requirements of the vitrification form agent of the MPC solidified liquid with HLW at different heat-treatment temperatures,which showed obvious advantages of MPC in solidifying the HLW.
作者 傅明娇 杨海林 吴传明 张影 尤超 钱觉时 FU Mingjiao;YANG Hailin;WU Chuanming;ZHANG Ying;YOU Chao;QIAN Jueshi(College of Materials Science and Engineering,Chongqing University,Chongqing 400045;College of Environment and Resources,Chongqing Technology and Business University,Chongqing 400067)
出处 《材料导报》 EI CAS CSCD 北大核心 2017年第24期86-90,共5页 Materials Reports
基金 国家自然科学基金国际合作项目(5141101039) 重庆市教委科学技术研究项目(KJ1600636)
关键词 高放核废液 固化 磷酸镁水泥 high-level radioactive waste immobilization MPC
  • 相关文献

参考文献3

二级参考文献24

  • 1张瑞珠,郭志猛,贾成厂,卢广峰,张华.自蔓延高温合成钙钛矿型人造岩石固化体[J].北京科技大学学报,2004,26(5):485-488. 被引量:14
  • 2汪宏涛,曹巨辉.军事工程用磷酸盐水泥材料研究[J].后勤工程学院学报,2005,21(1):5-7. 被引量:33
  • 3中国科学院贵阳地球化学研究所.简明地球化学手册[M].北京:科学出版社,1977.331-331.
  • 4汤宝龙(译) 考夫曼B.西德商用后处理高放废物固化物的评价.核燃料循环中放射性废物的处理和处置[M].北京:原子能出版社,1981.219-227.
  • 5汤宝龙(译) 考夫曼B.高放废物玻璃固化体的研制和辐照稳定性.核燃料循环中放射性废物的处理和处置[M].北京:原子能出版社,1981.209-218.
  • 6Weber W J, Ewing R C, Angell C A , Arnold G W. Radiation effects in glasses used for immobilization of high-level waste and plutonium disposition [J]. J. Mater. Res. , 1997, 12: 1946.
  • 7Ringwood A E, Kesson S E, Reeve K D, Zutze W, Ewing R. Synrroc [ A ]. In: Lutze W, Ewing R C, ed. Radioactive Waste Forms for the Formre [ M ]. Armsterdam : North Holland, 1988. 233.
  • 8Muthuraman M, Arul Dhas N, Patil K C. Commbustion synthesis of oxide materials for nuclear waste immobilization [ J]. Bull. Mater. Sci. , 1994, 17(6) : 977.
  • 9Borovinskaya I P, Barinova T V, Ratnikov V I, Zakorzhevsky V V, Ignatigeca T I. Consolidation of radioactives waste into mineral-like material by the SHS method [J]. Inter. J. SHS, 1998,7(1) : 129.
  • 10Barinova T V, Borovinskaya I P, Atnikov V I R, Ignatigeca T I, Zakorzhevsky V V. SHS Immobilization of radioactive wastes [J]. Kay Engineering Materials, 2002, 217: 193.

共引文献59

同被引文献47

引证文献4

二级引证文献25

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部