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Recovery of uranium and plutonium values from aqueous solutions of ammonium fluoride,particularly from zirflex-type waste solutions
Recovery of uranium and plutonium values from aqueous solutions of ammonium fluoride,particularly from zirflex-type waste solutions
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机译:从氟化铵水溶液中回收铀和p值,尤其是从Zirflex型废液中回收
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摘要
Uranium is recovered from an aqueous NH4F solution containing U and Zr by adding a soluble peroxide, e.g. 30% H2O2, to ppt. U peroxide (UO4.4H2O). The initial solution may be obtained by dissolving a Zr-clad UO2 fuel or a Zr-U alloy in 4-6 M. NH4FsBNH4NO3, and should have a maximum U concn. of 0.001 M. The temperature of pptn. may be 25-60 DEG C., and sufficient peroxide added to make the solution 0.1-3 M. in peroxide.
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机译:通过添加可溶的过氧化物,例如硫酸铵,从含有U和Zr的NH4F水溶液中回收铀。 30%H2O2,至ppt。过氧化铀(UO4.4H2O)。初始溶液可以通过将包覆Zr的UO2燃料或Zr-U合金溶解在4-6 M. NH4F sBNH4NO3中获得,并应具有最大的U concn。 0.001M。pptn的温度。可以为25-60℃,并加入足够的过氧化物以使溶液在过氧化物中为0.1-3M。
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