Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 3; Cement solidification experiment for phosphate effluent

Horiguchi, Kenichi ; Sugaya, Atsushi ; Tanaka, Kenji; Kobayashi, Kentaro; Sasaki, Tadashi*

In Nuclear Fuel Reprocessing Plant, it is necessary to dispose of a large amount of low level radioactive effluent safely and economically. In JAEA engineering developments concerning a cement solidification process have been carried out. The phosphate effluent occurring from solvent waste treatment facility is based on sodium dihydrogen phosphate. The acidity of this effluent (pH 4) requires a pre-treatment process before cement solidification. Phosphate effluent interfere with cementing reactions by retard of reaction rate and loss of strength, because it is combined with calcium that is element of cement material. It reports on the result of Non-radioactive simulant was prepared for the phosphate effluent, and used in cementation trials to investigate a special slag cement, on a beaker scale and at full scale (200-litres).