Process for treating radioactive waste liquid
US4804498A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Dec 8, 1986 |
| Grant date | Feb 14, 1989 |
| Priority date | — |
| Expiry date | Dec 8, 2006 |
Classification
- Technology area (CPC G)Physics
- CPC primaryG21F9/302
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
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.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.