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MECHANISTIC MODELING OF NUCLEAR WASTE FORM LEACHING BY AQUEOUS SOLUTIONS.

机译:水溶液中核废料形态浸出的力学模拟。

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摘要

Predictive modeling of nuclear waste form leaching requires a mechanistic representation of the processes and factors controlling the rates at which species are released from the solid waste form into the contacting aqueous solution. A basic distinction is made among bulk, surface, and leachant species, as well as between major (i.e., network formers) and minor (i.e., network modifiers) constituents of the solid structure. Major constituents exhibit no mobility within the solid bulk. Minor constituents may migrate within the solid matrix according to an electrically-assisted diffusion process. When the major constituents of the solid network are released from the outer surface layer into the solution, a breakdown of this layer ensues. This corrosion of the solid matrix occurs at a rate limited by the solubility of the network formers in the aqueous medium. Forward and backward reactions of the solid-liquid interface are modeled through two phenomenological rate processes. After showing the relevance of the semi-infinite medium approximation for describing leaching, all identified, potentially rate-controlling leaching mechanisms are integrated into a mathematical formulation which also incorporates two important system parameters: the specimen surface area-to-solution volume ratio and the leachant renewal frequency. Asymptotic analysis of a linearized version of the model shows that predicted short- and long-term leaching behaviors are physically correct. Surface processes tend to be initially rate-controlling, while at longer times dilution conditions of the leachant determine the rate-determining mechanism. Under dynamic leaching conditions, network dissolution eventually controls the leaching process whereas under static conditions bulk diffusion eventually prevails. The non-linear version of the model has been adapted to sodium and silicon leaching from borosilicate glass in deionized water, and fully implemented on computer by using a numerical strategy. The resulting code has been named LIX. This more complex version upholds the conclusions reached by the asymptotic analysis. Moreover, when tested against actual PNL 76-68 glass leaching data, LIX shows excellent capabilities in reproducing the experimental evidence, in particular the effects of the surface area-to-solution volume ratio.
机译:核废料形式浸出的预测模型需要以机械方式表示过程和控制速率,这些过程和因素控制着物质从固体废料形式释放到接触水溶液中的速率。在主体,表面和浸出物种类之间,以及在固体结构的主要成分(即网络形成剂)和次要成分(即网络改性剂)之间进行了基本区分。主要成分在固体内部没有流动性。微量成分可能会根据电辅助扩散过程在固体基质中迁移。当固体网络的主要成分从外表面层释放到溶液中时,该层将发生破裂。固体基质的腐蚀发生速率受网络形成剂在水性介质中的溶解度限制。固液界面的向前和向后反应是通过两个现象学速率过程建模的。在显示了用于描述浸出的半无限介质近似的相关性之后,所有已确定的,可能进行速率控制的浸出机制被整合到一个数学公式中,该公式还包含两个重要的系统参数:样品表面积与溶液的体积比和浸出剂更新频率。模型线性化版本的渐近分析表明,预测的短期和长期浸出行为在物理上是正确的。表面过程起初倾向于控制速率,而在更长的时间里,浸出剂的稀释条件决定了速率确定机制。在动态浸出条件下,网络溶解最终控制了浸出过程,而在静态条件下,主体扩散最终占主导。该模型的非线性版本已适应去离子水中硼硅酸盐玻璃中钠和硅的浸出,并通过使用数值策略在计算机上完全实现。结果代码已命名为LIX。这个更复杂的版本支持渐近分析得出的结论。此外,当根据实际的PNL 76-68玻璃浸出数据进行测试时,LIX在复制实验证据(特别是表面积与溶液体积比的影响)方面显示出卓越的能力。

著录项

  • 作者

    PESCATORE, CLAUDIO.;

  • 作者单位

    University of Illinois at Urbana-Champaign.;

  • 授予单位 University of Illinois at Urbana-Champaign.;
  • 学科 Nuclear engineering.
  • 学位 Ph.D.
  • 年度 1983
  • 页码 167 p.
  • 总页数 167
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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