Process for treating radioactive waste liquid

Compositions – Radioactive compositions

Patent

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Details

210682, 210687, 210712, 210751, 252631, 252632, 252635, 423158, 423166, 423179, 423183, 423184, 423199, G21F 916, G21F 908

Patent

active

048044989

ABSTRACT:
A soluble salt (sodium sulfate or sodium borate (Na.sub.2 SO.sub.4 or Na.sub.2 B.sub.4 O.sub.7) contained as the main component in a concentrated radioactive waste liquid generated in the BWR power plant or the PWR power plant is insolubilized and precipitated, sodium hydroxide (NaOH formed in the insolubilization is separated from the precipitate and the radioactive waste liquid slurry containing the precipitate is solidified with a hydraulic solidifying material. Since the separated caustic soda (NaOH) is free of radioactive substances, it can be easily utilized again, and since the radioactive substances are stably fixed in the solidified body, leakage of radioactivity from the solidified body can be greatly reduced.

REFERENCES:
patent: 4156646 (1979-05-01), Schulz
patent: 4265861 (1981-05-01), Cleary et al.
patent: 4448711 (1984-05-01), Motojima et al.
patent: 4476048 (1984-10-01), Ambros et al.
patent: 4620947 (1986-11-01), Carlson
patent: 4671897 (1987-06-01), Mori et al.

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