Process for treating radioactive waste
US4361505A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Jan 31, 1980 |
| Grant date | Nov 30, 1982 |
| Priority date | — |
| Expiry date | Jan 31, 2000 |
Classification
- Technology area (CPC G)Physics
- CPC primaryG21F9/167
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
N-.beta.-(aminoethyl)-.gamma.-aminopropyltrimethoxysilane [NH.sub.2 (CH.sub.2).sub.2 NH(CH.sub.2).sub.3 Si(OCH.sub.3).sub.3 ] as a silane coupling agent and SiO.sub.(2-x) (ONa).sub.x/2 (OH).sub.x/2 as colloidal silica are mixed into a radioactive liquid waste containing sodium sulfate as a main component, coming from a boiling water-type, nuclear power plant as an effluent. The resulting mixed radioactive liquid waste is supplied into a vessel provided with a rotating shaft with blades. The rotating shaft is revolved while heating the radioactive liquid waste in the vessel, thereby making the radioactive liquid waste into powder. The resulting powder containing the silane coupling agent and the colloidal silica is shaped into pellets by a pelletizer. The pellets having a low hygroscopicity and a high strength are obtained.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.