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

机译:HDPE土工膜中的抗氧化剂枯竭暴露于低水平放射性废物渗滤液

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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:低水平的放射性废物(LLW)和混合废物(MW)在美国的处理设施必须具有超过1000年的使用寿命。理解LLW和MW设施中使用的高密度聚乙烯(HDPE)土工膜的降解率是评估其使用寿命的必要条件。 HDPE土工膜(GM)在三个阶段进行降解:抗氧化耗竭(Ⅰ期),聚合物降解发作的诱导时间(Ⅱ期)和聚合物性质降解(Ⅲ期)。本文侧重于LLW渗滤液中的抗氧化枯萎病。 HDPE土工膜优惠券(2毫米厚)浸入放射性合成渗滤液(RSL)中,具有由美国能源部的环境恢复计划运营的LLW处置设施中的渗滤液中的化学。在四个温度(25,50,70和90℃)下评估耗尽。为了鉴定放射性核素对抗氧化剂耗尽的影响,除了排除放射性核素之外,用具有与RSL渗滤液相同的化学性的非放射性合成渗滤液(NSL)进行比较试验。用去离子水进行控制试验。定期除去标本并测试以确定其机械和化学性质。通过标准和高压氧化诱导时间(OIT)测试测量抗氧化耗尽。抗氧化剂耗竭速率随曝光温度的增加,浸入RSL中的GMS较高。 Arrhenius建模用于将实验室数据推断到15°C的典型LLW衬里。在复合衬垫中预测的抗氧化时间抗氧化耗尽为624年。

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