method for extraction of molybdenum - 99 from neutron irradiated, fissile materials and fission products containing matrix

摘要

The parent patent discloses the extraction of Mo-99 from a matrix contg. neutron irradiated fission prods, by digesting the matrix in an aq. alkali hydroxide soln., separating the soln. contg. Mo-99 from the residue of actinides and lanthanides, adding a mineral acid to the soln., and forming a complex of Mo-99 by addn. of thiocyanate ions, the treatment being carried out in 7 steps. The method is simplified in that the acidified soln. is treated with a thiocyanate ion contg. soln. having a SCN- concn. of 0.01 mole/l - 0.5 mole/l and subsequently with a previously conditioned organic ion exchanger of chelate forming synthetic resin type based on a styrene-divinylbenzene copolymer which contains methylene-nitriolidiacetate functional gps. and having a particle size of 35-840 mu to effect a selective sorption. The addn. of metallic Zn or Al and a reducing agent such as H, is not therefore required.