Method of disposing radioactive ion exchange resin
US4636335A · kind A · utility
17Cited by
9References
16Claims
0Family size
Assignee
Inventors
Key dates
| Filing date | Dec 7, 1983 |
| Grant date | Jan 13, 1987 |
| Priority date | — |
| Expiry date | Dec 7, 2003 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY10S159/12
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A method for processing spent radioactive ion exchange resin formed in a nuclear power plant by a two-step pyrolysis method. First, the spent resin is heated at 350.degree. C. to decompose functional groups selectively. Then the base polymer, formed as residue, is decomposed at a temperature above 350.degree. C., e.g. 600.degree. C. After the thermal decomposition, exhaust gases which require a special exhaust gas disposal means, such as NO.sub.x and SO.sub.x can be reduce to below 1/20.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.