Abstract
Decontamination properties of radioactive liquid waste treatment facilities were studied from the data of radioactive concentration measured before and after the treatment.
Evaporation treatment showed an excellent decontamination property, and every radioactivity of total α, total βγ and five important nuclides was not detected after this treatment.
By chemical coagulation, total ã radioactivity was effectively removed, but total βγ radioactivity was not. The DFs for total βγ radioactivity distributed between one and ten according to the nuclides contained in liquid waste. DF values of about ten were obtained for 60Co, 65Zn and 54Mn, and 137Cs was almost not removed. The removal of 51Cr lay between these two cases.
The treatment using organic ion exchange resin (Na+ form) removed every nuclides except 137Cs, but was not sufficiently effective for 137Cs. When 137Cs exists in liquid waste, it is necessary to use a vermiculite column after the treatment of chemical coagulation and/or ion exchange.
