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对从库莱布拉白云石完整岩芯柱的非破坏性和破坏性测试后分析中获得的锕系元素分布数据的解释。

Interpretation of actinide-distribution data obtained from non-destructive and destructive post-test analyses of an intact-core column of Culebra dolomite.

作者信息

Perkins W G, Lucero D A

机构信息

WIPP Regulatory Compliance Department, Sandia National Laboratories, Albuquerque, NM 87185-1395, USA.

出版信息

J Contam Hydrol. 2001 Feb;47(2-4):107-16. doi: 10.1016/s0169-7722(00)00141-8.

Abstract

The US Department of Energy (DOE), with technical assistance from Sandia National Laboratories, has successfully received EPA certification and opened the Waste Isolation Pilot Plant (WIPP), a nuclear waste disposal facility located approximately 42 km east of Carlsbad, NM. Performance assessment (PA) analyses indicate that human intrusions by inadvertent, intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides from the disposal system. For long-term brine releases, migration pathways through the permeable layers of rock above the Salado formation are important. Major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer overlying the WIPP site. In order to help quantify parameters for the calculated releases, radionuclide transport experiments have been carried out using intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the WIPP site. This paper deals primarily with results of analyses for 241Pu and 241Am distributions developed during transport experiments in one of these cores. Transport experiments were done using a synthetic brine that simulates Culebra brine at the core recovery location (the WIPP air-intake shaft (AIS)). Hydraulic characteristics (i.e., apparent porosity and apparent dispersion coefficient) for intact-core columns were obtained via experiments using the conservative tracer 22Na. Elution experiments carried out over periods of a few days with tracers 232U and 239Np indicated that these tracers were weakly retarded as indicated by delayed elution of the species. Elution experiments with tracers 241Pu and 241Am were attempted but no elution of either species has been observed to date, including experiments of many months' duration. In order to quantify retardation of the non-eluted species 241Pu and 241Am after a period of brine flow, non-destructive and destructive analyses of one intact-core column were carried out to determine distribution of these actinides in the rock. Analytical results indicate that the majority of the 241Am remained very near the injection surface of the core (possibly as a precipitate), and that the majority of the 241Pu was dispersed with a very high apparent retardation value. The 241Pu distribution is interpreted using a single-porosity advection-dispersion model, and an approximate retardation value is reported.

摘要

在美国能源部(DOE)的领导下,桑迪亚国家实验室提供技术支持,成功获得美国环境保护局(EPA)认证,并启用了废物隔离中试工厂(WIPP),这是一个位于新墨西哥州卡尔斯巴德以东约42公里处的核废料处置设施。性能评估(PA)分析表明,因资源勘探而导致的无意、间歇性人为侵入,是处置系统中放射性核素大量释放的唯一可信机制。对于长期盐水释放而言,通过萨拉多地层上方渗透岩层的迁移路径至关重要。重点关注的是拉斯特勒地层的库莱布拉段,因为它是WIPP场地之上渗透性最强的地质层。为了帮助量化计算释放量的参数,利用从WIPP场地内拉斯特勒地层的库莱布拉白云岩段获取的完整岩芯柱进行了放射性核素迁移实验。本文主要论述了在其中一个岩芯的迁移实验过程中得出的关于241Pu和241Am分布的分析结果。迁移实验使用的是一种模拟库莱布拉段在岩芯采集点(WIPP进气竖井(AIS))处盐水的合成盐水。通过使用保守示踪剂22Na的实验,获得了完整岩芯柱的水力特性(即表观孔隙率和表观弥散系数)。使用示踪剂232U和239Np进行了为期数天的洗脱实验,结果表明,这些示踪剂的洗脱出现延迟,说明它们的滞留作用较弱。尝试使用示踪剂241Pu和241Am进行洗脱实验,但迄今为止,尚未观察到任何一种示踪剂出现洗脱现象,包括持续数月的实验。为了量化在一段时间的盐水流动后未洗脱的241Pu和241Am的滞留情况,对一根完整岩芯柱进行了无损和有损分析,以确定这些锕系元素在岩石中的分布。分析结果表明大部分241Am仍非常靠近岩芯的注入表面(可能以沉淀物形式存在),并且大部分241Pu以非常高的表观滞留值分散分布。使用单孔隙度对流弥散模型对241Pu的分布进行了解释,并报告了一个近似的滞留值。

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