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首页> 外文期刊>Progress in Nuclear Energy >Dissolution of synthetic uranium dibutyl phosphate (U-DBP) in sodium EDTA and sodium carbonate based formulations
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Dissolution of synthetic uranium dibutyl phosphate (U-DBP) in sodium EDTA and sodium carbonate based formulations

机译:合成磷酸二铀铀(U-DBP)在EDTA钠和碳酸钠配方中的溶解

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摘要

Nuclear fuel reprocessing facilities that use tributyl phosphate (TBP) and nitric acid tend to develop a sticky coating of uranium dibutyl phosphate (U-DBP) on their surfaces. This sticky coating also gets formed on the reprocessing waste storage tanks on long standing, which results in radiation exposure hazard. Hence, it is required to periodically dissolve U-DBP deposits. Investigations on the dissolution of synthetic U-DBP in powder form with EDTA, disodium salt of EDTA (Na-2-EDTA) and sodium carbonate (Na2CO3) have been investigated. Studies were also carried out with hydrogen peroxide (H2O2) as the oxidizing agent, though due caution has to be exercised while handling it apart from the undesirable corrosion of structural materials. Of the formulations evaluated, 1% Nat-EDTA containing 1% H2O2 and 0.5% Na2CO3 were found to yield more than 90% dissolution. On considering the disadvantages of H2O2, sodium carbonate is considered to be suitable for the dissolution of U-DBP. (C) 2017 Elsevier Ltd. All rights reserved.
机译:使用磷酸三丁酯(TBP)和硝酸的核燃料后处理设施往往会在其表面形成粘性的磷酸二丁酯(U-DBP)涂层。这种粘性涂层长期放置在后处理废物存储罐上也会形成,这会导致辐射暴露危险。因此,需要定期溶解U-DBP沉积物。研究了用EDTA,EDTA二钠盐(Na-2-EDTA)和碳酸钠(Na2CO3)溶解粉末状合成U-DBP的方法。还使用过氧化氢(H2O2)作为氧化剂进行了研究,尽管除了结构材料的不期望的腐蚀外,在处理它时必须谨慎行事。在所评估的制剂中,发现含有1%H2O2和0.5%Na2CO3的1%Nat-EDTA溶解度超过90%。考虑到H2O2的缺点,碳酸钠被认为适合U-DBP的溶解。 (C)2017 Elsevier Ltd.保留所有权利。

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