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

机译:消除水银去除预处理对高水平放射性废物熔断器近酷胶系统的影响

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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%. An 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 matched the 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:Savannah河河网站的防御废物处理设施从含有溶解和沉淀金属和放射性核素的核材料加工过程中加工高级放射性废物。在地质储存库中玻璃化入硼硅酸盐玻璃,以实现在地质储存库中的最终处理,包括化学改变废物以使其与玻璃熔化系统相容。预处理步骤包括通过溶解和洗涤除去过量的铝,用甲酸和硝酸加工为:1)调节玻璃熔化中的还原氧化(氧化还原)电位,以降低放射性核素挥发性并提高熔融率; 2)调整饲料流变学; 3)通过汽提的蒸汽剥离必须在熔化中加工的汞的量。已经提出了消除甲酸预处理以消除预处理系统中的氢的产生;替代还原剂将用于控制氧化还原。然而,消除甲酸将导致复合饲料中的汞显着更多;目前规格不超过0.45重量%,而预处理前的最大预期约为2.5重量%。已经进行了一种工程研究来估算消除汞拆除对熔毒剂系统性能的影响。开发了均相气相氧化模型和水相模型,以研究DWPF Melter Offgas系统中汞的形态。该模型针对可用的实验数据进行校准,然后应用于DWPF条件。气相模型准确地预测(Hg_2)〜(2 +)/ hg〜(2+)比,但仍然存在一些未氧化的Hg〜0。含有小于1mM Cl_2的水性模型表明,该剩余的Hg〜0将被氧化,使得最终(Hg_2)〜(2 +)/ hg〜(2+)比率匹配实验数据。将模型应用于DWPF的结果表明,由于氯化物的缺水过高,只有6%的汞饲料预计将被氯化,主要是Hg_2Cl_2,而剩余的汞将存在于元素汞(90%)或HgO中存在(4%)。

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