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Antioxidant Depletion in HDPE Geomembranes Exposed to Low-Level Radioactive Waste Leachate

机译:暴露于低放射性废物渗滤液的HDPE土工膜中的抗氧化剂消耗

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Low-level radioactive waste (LLW) and mixed waste (MW) disposal facilities in the US are required to have a service life in excess of 1000 yr. Understanding the rate of degradation of high-density polyethylene (HDPE) geomembranes used in LLW and MW facilities is necessary to assess their service life. HDPE geomembranes (GM) undergo degradation in three stages: antioxidant depletion (Stage Ⅰ), induction time to the onset of polymer degradation (Stage Ⅱ), and polymer property degradation (Stage Ⅲ). This paper focuses on antioxidant depletion in LLW leachate. HDPE geomembrane coupons (2-mm thick) were immersed in radioactive synthetic leachate (RSL) with chemistry representative of leachate in LLW disposal facilities operated by the US Department of Energy's environmental restoration programs. Depletion was assessed at four temperatures (25, 50, 70, and 90 °C). To identify the effect of radionuclides on antioxidant depletion, comparative tests were conducted with non-radioactive synthetic leachate (NSL) having the same chemistry as the RSL leachate, except radionuclides were excluded. Control tests were conducted with deionized water. Specimens were removed periodically and tested to determine their mechanical and chemical properties. Antioxidant depletion was measured by both standard and high-pressure oxidative induction time (OIT) tests. The antioxidant depletion rate increased with exposure temperature and was higher for GMs immersed in RSL. Arrhenius modeling was used to extrapolate the laboratory data at elevated temperatures to a typical LLW liner at 15 °C. The predicted time to antioxidant depletion for a GM in a composite liner is 624 yr.
机译:美国的低放射性废物(LLW)和混合废物(MW)处置设施的使用寿命必须超过1000年。了解用于LLW和MW设施的高密度聚乙烯(HDPE)土工膜的降解速率对于评估其使用寿命是必要的。 HDPE土工膜(GM)经历了三个阶段的降解:抗氧化剂消耗(阶段Ⅰ),诱导聚合物降解开始的时间(阶段Ⅱ)和聚合物性质降解(阶段Ⅲ)。本文重点研究了低渗沥滤液中抗氧化剂的消耗。将HDPE土工膜(厚度为2毫米)浸入放射性合成渗滤液(RSL)中,渗滤液的化学代表在美国能源部环境恢复计划运营的LLW处置设施中。在四个温度(25、50、70和90°C)下评估损耗。为了确定放射性核素对抗氧化剂消耗的影响,使用化学性质与RSL浸出液相同的非放射性合成浸出液(NSL)进行了比较测试,但不包括放射性核素。用去离子水进行对照测试。定期取出样品并进行测试以确定其机械和化学性能。通过标准和高压氧化诱导时间(OIT)测试来测量抗氧化剂的消耗。抗氧化剂的耗竭率随着暴露温度的升高而增加,而浸泡在RSL中的GM的抗氧化剂耗竭率更高。使用Arrhenius建模将温度升高时的实验室数据外推到15°C下的典型LLW衬管。复合材料衬里中的GM的抗氧化剂消耗的预计时间为624年。

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