Development of Chemical Processes and Equipment to Recover Curium-244 and Californium-252
Development of Chemical Processes and Equipment to Recover Curium-244 and Californium-252
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回收锔244和锎252的化学工艺和设备的开发
DOI：
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发表时间：
2008
期刊：
影响因子：
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通讯作者：
J. T. Lowe
中科院分区：
文献类型：
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作者：
R. M. Harbour;C. Ice;W. H. Hale;J. T. Lowe
244Cm 和 252Cf 在 20 世纪 60 年代中期，在萨凡纳河基地 (SRS) 在设计用于连续中子俘获的核反应堆辐照中使用 239Pu 原材料生产了 244Cm 和 252Cf。萨凡纳河实验室 (SRL) 开发了溶剂萃取和离子交换工艺及设备，用于从辐照钚铝燃料管中分离和纯化锔和锎。事实证明，高压离子交换比叔胺溶剂萃取工艺（“Tramex”）更适合纯化的最后阶段。高压置换和洗脱发展阳离子交换色谱过程的组合能够分离和纯化100克量的244Cm和毫克量的252Cf。 Curium-244 适合作为远程应用的同位素电源，252Cf 是用于医疗和工业应用的强中子源。
In the mid 1960s, 244Cm and 252Cf were produced at the Savannah River Site (SRS) from 239Pu starting material in nuclear reactor irradiations designed for successive neutron capture. Both solvent extraction and ion exchange processes and equipment were developed at the Savannah River Laboratory (SRL) to separate and purify curium and californium from irradiated plutonium-aluminum fuel tubes. High-pressure ion exchange proved more suitable than a solvent extraction process with tertiary amines (“Tramex”) for the final stages of purification. A combination of high-pressure displacement and elution development cation exchange chromatographic processes was able to separate and purify 100 g quantities of 244Cm and milligram quantities of 252Cf. Curium-244 is suitable as an isotopic power source for remote applications, and 252Cf is an intense neutron source for medical and industrial applications.