首页> 外文会议>8th International Conference on Radioactive Waste Management and Environmental Remediation >METHODOLOGY IN CORROSION TESTING OF CONTAINER MATERIALS FOR RADIOACTIVE WASTE DISPOSAL IN A GEOLOGICAL CLAY REPOSITORY
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METHODOLOGY IN CORROSION TESTING OF CONTAINER MATERIALS FOR RADIOACTIVE WASTE DISPOSAL IN A GEOLOGICAL CLAY REPOSITORY

机译:地质粘土处置场中放射性废物处理容器材料的腐蚀测试方法

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The current worldwide trend for the final disposal of conditioned high-level, medium-level and long-lived alpha-bearing radioactive waste focuses on deep geological disposal. During the geological disposal, the isolation between the radioactive waste and the environment (biosphere) is realised by the multibarrier principle, which is based on the complementary nature of the various natural and engineered barriers. One of the main engineered barriers is the metallic container (overpack) that encloses the conditioned waste. In Belgium, the Boom Clay sediment is being studied as a potential host rock formation for the final disposal of conditioned high-level radioactive waste (HLW) and spent fuel. Since the mid 1980's, SCK*CEN has developed an extensive research programme aimed at evaluating the suitability of a wide variety of metallic materials as candidate overpack material for the disposal of HLW. A multiple experimental approach is applied consisting of ⅰ) in situ corrosion experiments, ⅱ) electrochemical experiments (cyclic potentiodynamic polarisation measurements and monitoring the evolution of E_(CORR) as a function of time), and ⅲ) immersion experiments. The in situ corrosion experiments were performed in the underground research facility, the High Activity Disposal Experimental Site, or HADES, located in the Boom clay layer at a depth of 225 metres below ground level. These experiments aimed at predicting the long-term corrosion behaviour of various candidate container materials. It was believed that this could be realised by investigating the medium-term interactions between the container materials and the host formation. These experiments resulted in a change of reasoning at the national authorities concerning the choice of over-pack material from the corrosion-allowance material carbon steel towards corrosion-resistant materials such as stainless steels. The main arguments being the severe pitting corrosion during the aerobic period and the large amount of hydrogen gas generated during the subsequent anaerobic period. The in situ corrosion experiments however, did not allow to unequivocally quantify the corrosion of the various investigated candidate overpack materials. The main shortcoming was that they did not allow to experimentally separate the aerobic and anaerobic phase. This resulted in the elaboration of a new laboratory programme. Electrochemical corrosion experiments were designed to investigate the effect of a wide variety of parameters on the localised corrosion behaviour of candidate overpack materials: temperature, SO_4~(2-), Cl~-, S_2O_3~(2-), oxygen content (aerobic - anaerobic),... Three characteristic potentials can be derived from the cyclic potentiodynamic polarisation (CPP) curves: ⅰ) the open circuit potential, OCP, ⅱ) the critical potential for pit nucleation, E_(NP), and ⅲ) the protection potential, E_(PP). Monitoring the open circuit potential as a function of time in clay slurries, representative for the underground environment, provides us with a more reliable value for the corrosion potential, E_(CORR), under disposal conditions. The long-term corrosion behaviour of the candidate overpack materials can be established by comparing the value of E_(CORR) relative to E_(NP) and E_(PP) (determined from the CPP-curves). The immersion tests were developed to complement the in situ experiments. These experiments aimed at determining the corrosion rate and to identify the corrosion processes that can occur during the aerobic and anaerobic period of the geological disposal. Also, some experiments were elaborated to study the effect of graphite on the corrosion behaviour of the candidate overpack materials.
机译:当前在全球范围内处理条件化的高,中,长寿命含阿尔法放射性废物的最终趋势集中在深部地质处置上。在地质处置过程中,放射性废物与环境(生物圈)之间的隔离是通过多屏障原理实现的,该原理基于各种自然屏障和工程屏障的互补性质。工程隔离的主要障碍之一是封闭处理过的废物的金属容器(外包装)。在比利时,正在对动臂粘土沉积物进行研究,将其作为最终处置条件化高放射性废物(HLW)和乏燃料的潜在宿主岩层。自1980年代中期以来,SCK * CEN制定了一项广泛的研究计划,旨在评估各种金属材料作为处理高放废物的候选外包装材料的适用性。应用了多种实验方法,包括ⅰ)原位腐蚀实验,ⅱ)电化学实验(循环电势极化测量和监视E_(CORR)随时间的变化)和,)浸入实验。原位腐蚀实验是在位于地下黏土深达225米的Boom黏土层中的地下研究设施,高活性处置试验场或HADES中进行的。这些实验旨在预测各种候选容器材料的长期腐蚀行为。据信,这可以通过研究容器材料与基质形成之间的中期相互作用来实现。这些实验导致国家主管部门改变了关于选择外包装材料的理由,从允许腐蚀的材料碳钢到诸如不锈钢的耐腐蚀材料。主要论点是在好氧时期出现严重的点蚀,在随后的厌氧时期产生大量的氢气。然而,原位腐蚀实验不允许明确地量化各种研究过的候选外包装材料的腐蚀。主要缺点是它们不允许实验分离好氧和厌氧相。这导致制定了新的实验室计划。设计电化学腐蚀实验来研究各种参数对候选外包装材料局部腐蚀行为的影响:温度,SO_4〜(2-),Cl〜-,S_2O_3〜(2-),氧含量(好氧-厌氧),...可以从循环电势极化(CPP)曲线得出三个特征电势:ⅰ)开路电势,OCP,ⅱ)凹坑成核的临界电势,E_(NP),以及ⅲ)保护电位E_(PP)。监测代表地下环境的粘土浆液中随时间变化的开路电势,可以为我们提供在处置条件下更可靠的腐蚀电势E_(CORR)值。可以通过比较E_(CORR)相对于E_(NP)和E_(PP)的值(由CPP曲线确定)来确定候选外包装材料的长期腐蚀行为。开发了浸没测试以补充原位实验。这些实验旨在确定腐蚀速率并确定在地质处置的好氧和厌氧期间可能发生的腐蚀过程。此外,还精心设计了一些实验来研究石墨对候选外包装材料腐蚀行为的影响。

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