Invention Grant
US07749469B2 Process for recovering isolated uranium from spent nuclear fuel using a highly alkaline carbonate solution 有权
使用高碱性碳酸盐溶液从废核燃料中回收分离的铀的方法

Process for recovering isolated uranium from spent nuclear fuel using a highly alkaline carbonate solution
Abstract:
Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.
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