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SEPARATION OF FISSION PRODUCTS AND ACTINIDES FROM SAVANNAH RIVER SITE HIGH-LEVEL NUCLEAR WASTES

机译:裂变产品与萨凡纳河网站高级核废物的散浮液分离

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Separation methods for the pretreatment of the liquid fraction of high-level nuclear waste (HLW) at the Savannah River Site (SRS) include solvent extraction for the separation of cesium and adsorption/ion exchange for the removal of strontium and alpha-emitting actinides. The solvent extraction process, referred to as Caustic Side Solvent Extraction or CSSX, uses a calixarene extractant in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline material for the removal of strontium and alpha-emitting radionuclides (principally ~(238)Pu, ~(239)Pu, ~(240)Pu and ~(237)Np). Two pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year. The same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters per year, is scheduled to begin radioactive operations in 2013. This paper presents an overview of the separation processes as well as recent research and development activities aimed at improving separation performance in the pretreatment facilities.
机译:在萨凡纳河河网站(SRS)的高水平核废物(HLW)液体分数的分离方法包括用于分离铯和吸附/离子交换的溶剂萃取,用于去除锶和α-发光的散曲线。溶剂萃取过程称为腐蚀性侧溶剂萃取或CSSX,用含烃稀释剂中的相改性剂组合使用钙碱提取物。钛酸钠(MST)是含水金属氧化物,是用于去除锶和α发射放射性核素的基线材料(主要是〜(238)PU,〜(239)PU,〜(240)PU和〜(237)NP )。两个预处理设施,模块化腐蚀侧溶剂提取单元(MCU)和Actinide移除过程(ARP)设施于2008年开始于SRS。这些设施每年可以治疗约400万升余地。还计划用于更大的盐废物处理设施(SWPF)的相同的分离过程。该SWPF每年的设计吞吐量约为2700万升,计划在2013年开始放射性运营。本文概述了分离过程以及最近的研发活动,旨在提高预处理中的分离性能设施。

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