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Impact of Eliminating Mercury Removal Pretreatment on the Performance of a High Level Radioactive Waste Melter Offgas System

机译:消除汞去除预处理对高水平放射性废物熔炉废气系统性能的影响

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The Defense Waste Processing Facility at the Savannah River Site processes high-level radioactive waste from the processing of nuclear materials that contains dissolved and precipitated metals and radionuclides. Vitrification of this waste into borosilicate glass for ultimate disposal at a geologic repository involves chemically modifying the waste to make it compatible with the glass melter system. Pretreatment steps include removal of excess aluminum by dissolution and washing, and processing with formic and nitric acids to: 1) adjust the reduction-oxidation (redox) potential in the glass melter to reduce radionuclide volatility and improve melt rate; 2) adjust feed rheology; and 3) reduce by steam stripping the amount of mercury that must be processed in the melter. Elimination of formic acid pretreatment has been proposed to eliminate the production of hydrogen in the pretreatment systems; alternative reductants would be used to control redox. However, elimination of formic acid would result in significantly more mercury in the melter feed; the current specification is no more than 0.45 wt%, while the maximum expected prior to pretreatment is about 2.5 wt%.rnAn engineering study has been undertaken to estimate the effects of eliminating mercury removal on the melter offgas system performance. A homogeneous gas-phase oxidation model and an aqueous phase model were developed to study the speciation of mercury in the DWPF melter offgas system. The model was calibrated against available experimental data and then applied to DWPF conditions. The gas-phase model predicted the Hg_2~(2+) /Hg~(2+) ratio accurately, but some un-oxidized Hg~0 remained. The aqueous model, with the addition of less than 1 mM Cl_2 showed that this remaining Hg~0 would be oxidized such that the final Hg_2~(2+) /Hg~(2+) ratios matchedrnthe experimental data. The results of applying the model to DWPF show that due to excessive shortage of chloride, only 6% of the mercury fed is expected to be chlorinated, mostly as Hg_2Cl_2, while the remaining mercury would exist either as elemental mercury (90%) or HgO (4%).
机译:萨凡纳河站点的国防废物处理设施处理含有溶解和沉淀的金属和放射性核素的核材料加工过程中产生的高放射性废物。将该废物玻璃化为硼硅酸盐玻璃,以便最终在地质处置库处置,这涉及对废物进行化学改性以使其与玻璃熔化器系统兼容。预处理步骤包括通过溶解和洗涤除去过量的铝,以及用甲酸和硝酸进行处理,以:1)调节玻璃熔化器中的还原氧化(redox)电势,以减少放射性核素的挥发性并提高熔化速率; 2)调整饲料流变性; 3)通过蒸汽汽提减少必须在熔化器中处理的汞量。已经提出消除甲酸预处理以消除预处理系统中氢气的产生。替代的还原剂将用于控制氧化还原。但是,消除甲酸会导致熔化炉进料中的汞明显增加。当前的规格不超过0.45 wt%,而预处理前的最大预期含量约为2.5 wt%。已进行了一项工程研究,以评估消除汞去除对熔炉废气系统性能的影响。建立了均相气相氧化模型和水相模型,以研究DWPF熔炉废气系统中汞的形态。针对可用的实验数据对模型进行了校准,然后将其应用于DWPF条件。气相模型可以准确地预测Hg_2〜(2+)/ Hg〜(2+)的比例,但仍存在一些未氧化的Hg〜0。加入少于1 mM Cl_2的水相模型表明,该残留的Hg〜0将被氧化,使得最终的Hg_2〜(2+)/ Hg〜(2+)比值与实验数据相符。将模型应用于DWPF的结果表明,由于氯化物的过度短缺,预计进料的汞中只有6%被氯化,主要是Hg_2Cl_2,而其余的汞将以元素汞(90%)或HgO的形式存在(4%)。

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