Process for treating radioactive waste
US5457266A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | May 18, 1994 |
| Grant date | Oct 10, 1995 |
| Priority date | — |
| Expiry date | May 18, 2014 |
Classification
- Technology area (CPC G)Physics
- CPC primaryG21F9/14
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A process for treating radioactive waste in the form of contaminated powdery ionic exchange resin to make it suitable for final storage by reducing its volume as much as possible, includes mechanically dewatering the ion exchange resin. The dewatered ion exchange resin is mixed with a calcium compound. The mixture is dried at temperatures of up to 120.degree. C. and preferably about 50.degree. C. to 60.degree. C., and at a pressure of from 120 to 200 hPa, until a residual moisture content of less than 10% of the mass of the mixture is reached. The dry mixture is thermally treated at a pressure below atmospheric pressure by heating up to a temperature of from at least 120.degree. C. to at most 190.degree. C. The ion exchange resin thereby loses its water absorption and swelling capability. Ion exchange resins treated in this manner are processed with cement or bitumen to form blocks that are suitable for final storage.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.