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U.S. Department of Energy
Office of Scientific and Technical Information

Method for noncontaminating solidification of radioactive waste materials

Patent ·
OSTI ID:5567095
Method is disclosed for the solidification, in a manner which protects the environment against contamination, of waste materials obtained during reprocessing of irradiated nuclear fuel and/or breeder materials in a matrix of borosilicate glass. Highly radioactive solutions or slurries containing the waste materials in dissolved or suspended form are evaporated in a vessel in the presence of glass former substances until they are dry, the dry residue is calcinated and the calcinate is melted together with the glass formers while the waste gases are discharged to the environment. The waste liquid is obtained from a reprocessing system without pretreatment, is mixed with glass formers and a reduction agent and then is introduced in a controlled, continuous manner into the center of a borosilicate glass melt disposed in a melting crucible at a temperature in the region of 1000* to 1400* C. To form an island-like drying and calcinating zone on the surface of the melt while avoiding contact of the waste liquid with the walls of the crucible. A reducing atmosphere is formed and the presence of components in the waste gas which would radiologically and/or chemically contaminate the environment are substantially avoided.
Assignee:
Gesellschaft Fur Kernforschung Mbh (Germany, Federal Republic of)
Patent Number(s):
US 4202792
OSTI ID:
5567095
Country of Publication:
United States
Language:
English