Removing method of technetium in liquid waste

The present invention concerns a method of selectively removing technetium from liquid wastes containing salts dissolved therein at a high concentration and discharged from processes of nuclear fuel handling facilities. The method comprises contacting the liquid wastes with particles of a strongly basic anion exchange resin having a water content of from 43 to 48% and a grain size of 0.3mm or less and having a trimethyl benzyl ammonium salt as an exchange group to adsorb and remove TcO4- by ion exchange. The method of contacting the liquid wastes with the predetermined anion exchange resin comprises filling particles of the strongly basic anion exchange resin into a column, and the liquid wastes are passed through the column. Subsequent to the contact, a strong acid is acted on the anion exchange resin adsorbed with TcO4-, and then eluted TcO4- is reduced, precipitated and separated in the form of TcO2 followed by solidification. Technetium can be adsorbed and removed selectively by a slight amount of an ion exchange resin. It is suffice to use an ordinary simple facility. (N.H.)