期刊文献+

高放玻璃固化体深地质处置过程中溶解机理分析与计算 被引量:1

Mechanism analysis and calculation of vitrified HLW dissolution due to ground water erosion in the process of geological disposal
下载PDF
导出
摘要 对高放玻璃固化体在地质处置过程中由于地下水的侵蚀而导致玻璃体溶解的溶解机理进行了分析,利用水解反应动力学模型对不同温度、不同pH条件下的玻璃固化体溶解速率进行了计算。计算结果表明:玻璃在酸性或高温情况下溶解速率较大,60℃、pH值6时平均溶解速率在0.35 g/a左右,120℃、pH值8.5时平均溶解速率在0.8 g/a左右;在100万年这个时间尺度上,120℃、pH值8.5时玻璃的最大溶解量是80%。考虑到地下处置库中温度一般要低于60℃,地下水的pH值范围在6-10,所以最保守估计100万年玻璃固化体的溶解侵蚀分数不大于50%。 The mechanism of vitrified HLW dissolution due to ground water erosion in the process of geological disposal is analyzed. Through hydrolysis reaction kinetics,dissolution rate of vitrified HLW is calculated with different temperatures and pH values,which comes out that dissolution rate is about 0. 35 g / a with 60 ℃ and pH 6,while dissolution rate is about 0. 8 g / a with 120 ℃ and pH 8. 5; and it can be concluded that there may be a trend for dissolution rate of vitrified HLW that increases with temperatures and acidity. Among the dimension of 1 million years,the maximum dissolution load of HLW vitrified waste is 80% with 120 ℃ and pH 8. 5. When considering that the disposal temperature at 60 ℃ and the range of ground water pH is 6—10,the most conservative estimated dissolution load of vitrified HLW is less than 50% over the dimension of 1 million years.
出处 《辐射防护》 CAS CSCD 北大核心 2016年第1期7-13,共7页 Radiation Protection
基金 国防科工局"十二五"地质处置安全评价技术研究(科工二司(2013)1221号)
关键词 高放废物玻璃固化体 深地质处置 溶解机理 vitrified HLW deep geological disposal dissolution mechanism
  • 相关文献

参考文献17

  • 1Dran JC, Petit JC, Brouse C. Mechanism of aqueous dissolution of silicate glasses yielded by fission tracks[J]. Nature, 1986, 319: 485- 487. 被引量:1
  • 2Hellmann R, Cotte S, Cadel E. Nanometre-seale evidence for interracial dissolution repreeipitation control of silicate glass corrosion [ J ]. Nature Materials , 2015, 14:306-311. 被引量:1
  • 3Cailleeteau C, Angeli F, Devreux F. Insight into silicate-glass corrosion mechanisms [ J ]. Nature Materials , 2008, 7 : 978 - 983. 被引量:1
  • 4Gin S, Jollivet P, Fournier M. The fate of silicon during glass corrosion under alkaline conditions: A mechanistic and kinetic study with the International Simple Glass [ J ]. Geochimica et Cosmochimica Acta, 2015, 151 : 68 - 85. 被引量:1
  • 5Frugier P, Gin S, Minet Y, et al. SON68 nuclear glass dissolution kinetics: Current state ofknowledge and basis of the new GRAAL model [J]. Journal of Nuclear Materials, 2008, 380:8 -21. 被引量:1
  • 6Quaranta A, Cattaruzza E, Gonella F. Modelling the ion exchange process in glass : Phenomenological approaches and perspectives [ J]. Materials Science & Engineering B, 2008, 149:133 - 139. 被引量:1
  • 7Ojovan M , Pankov A , Lee W. The ion exchange phase in corrosion of nuclear waste glasses [ J ]. Journal of Nuclear Materials, 2006, 358: 57 -68. 被引量:1
  • 8Gin S, Jegou C, Frugier P. Theoretical consideration on the application of the Aagaard - Helgeson rate law to the dissolution of silicate minerals and glasses [ J ]. Chemical Geology , 2008, 255:14 -24. 被引量:1
  • 9Ferrand K, Abdelouas A, Grambow B. Water diffusion in the simulated French nuclear waste glass SON68 contacting silica rich solutions: Experimental and modeling [ J ]. Journal of Nuclear Materials, 2006, 355 : 54 - 67. 被引量:1
  • 10Fournier M, Gin S, Frugier P. Resumption of nuclear glass alteration: State of the art [ J ]. Journal of Nuclear Materials, 2014, 448: 348 - 363. 被引量:1

同被引文献3

引证文献1

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