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Residual waste from Hanford tanks 241-C-203 and 241-C-204. 2. Contaminant release model

机译:汉福德(Hanford)油箱241-C-203和241-C-204的残余废物。 2.污染物释放模型

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Release of U and Tc-99 from residual sludge in Hanford waste tanks 241-C-203 and 241-C-204 at the U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington state was quantified by water-leaching, selective extractions, empirical solubility measurements, and thermodynamic modeling. A contaminant release model was developed based on these experimental results and solid-phase characterization results presented elsewhere. Uranium release was determined to be controlled by two phases and occurred in three stages. In the first stage, U release is controlled by the solubility of cejkaite, which is suppressed by high concentrations of sodium released from the dissolution of NaNO3 in the residual sludges. Equilibrium solubility calculations indicate the U released during this stage will have a maximum concentration of 0.021 M. When all the NaNO3 has dissolved from the sludge, the solubility of the remaining cejkaite will increase to 0.28 M. After cejkaite has completely dissolved, the majority of the remaining U is in the form of poorly crystalline Na2U2O7 [or clarkeite Na[(UO2)O(OH)](H2O)(0-1)]. In contact with Hanford groundwater this phase is not stable, and becquerelite becomes the U solubility controlling phase, with a calculated equilibrium concentration of 1.2 x 10(-4) M. For Tc, a significant fraction of its concentration in the residual sludge was determined to be relatively insoluble (20 wt % for C-203 and 80 wt % for C-204). Because of the low concentrations of Tc in these sludge materials, the characterization studies did not identify any discrete Tc solids phases. Release of the soluble fraction of Tc was found to occur concomitantly with NO3-. It was postulated that a NaNO3-NaTcO4 solid solution could be responsible for this behavior. The Tc release concentrations for the soluble fraction were estimated to be 2.4 x 10(-6) M for C-203 and 2.7 x 10(-5) M for C-204. Selective extraction results indicated that the recalcitrant fraction of Tc was associated with Fe oxides. Release of the recalcitrant fraction of Tc was assumed to be controlled by dissolution of Fe oxide in the form of ferrihydrite. Based on this assumption and measured values for the ratio of recalcitrant Tc to total Fe in each bulk sludge, the release concentration of the recalcitrant fraction of Tc was calculated to be 3.9 x 10(-12) M for C-203 and 10.0 x 10(-12) M for C-204.
机译:华盛顿州东南部美国能源部(DOE)汉福德厂区汉福德废料池241-C-203和241-C-204中残留污泥中的U和Tc-99的释放通过水浸,选择性提取,经验溶解度测量和热力学建模。基于这些实验结果和其他地方提出的固相表征结果,开发了污染物释放模型。确定铀的释放受两个阶段控制,并且分三个阶段发生。在第一阶段,U的释放是由Cejkaite的溶解度控制的,该溶解度被NaNO3在残留污泥中的溶解所释放的高浓度钠所抑制。平衡溶解度计算表明,在此阶段释放的U的最大浓度为0.021M。当所有NaNO3从污泥中溶解后,剩余的硅藻土的溶解度将增加至0.28M。在硅藻土完全溶解后,大部分其余的U则为结晶度较差的Na2U2O7 [或clarkeite Na [(UO2)O(OH)](H2O)(0-1)]形式。与汉福德地下水接触时,该相不稳定,珠光沸石成为U溶解度控制相,计算出的平衡浓度为1.2 x 10(-4)M。对于Tc,确定了其在残余污泥中的大部分浓度相对不溶(对于C-203为20重量%,对于C-204为80重量%)。由于这些污泥材料中Tc的浓度较低,因此表征研究未发现任何离散的Tc固相。发现Tc的可溶性部分的释放与NO3-一起发生。据推测,NaNO3-NaTcO4固溶体可能是造成这种现象的原因。对于C-203,可溶级分的Tc释放浓度估计为2.4 x 10(-6)M,对于C-204,估计为2.7 x 10(-5)M。选择性提取结果表明,Tc的顽固级分与Fe氧化物有关。假定Tc顽calc级分的释放受三水铁矿形式的Fe氧化物溶解的控制。基于此假设和每种散装污泥中顽固性Tc与总Fe的比值的测量值,对于C-203和10.0 x 10,Tc顽固性馏分的释放浓度计算为3.9 x 10(-12)M (-12)C-204的M。

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