FIELD: chemistry.
SUBSTANCE: invention relates to processing and recycling radioactive wastes from nuclear industry enterprises. According to the method, filter material is treated with aqueous solutions and then undergoes sorption or extraction purification from impurities. A metal salt is precipitated from sorption (extraction) purification solutions and then calcined until a metal oxide is obtained. The starting material containing uranium, boron and silicon is broken up in nitric acid with concentration (4.5±0.2) mol/l at temperature (105±2)°C for 2 to 3 hours. To remove silicon, diproxamine-157 flocculant is added to the nitric acid solution in amount of 0.10-0.25 mg per 1 l solution one hour before the end of the breaking up process.
EFFECT: high degree of purification from radioactive wastes.
1 tbl, 8 ex
Title | Year | Author | Number |
---|---|---|---|
METHOD OF PLATINUM GROUP METALS EXTRACTING FROM VOLOXIDIZED SNF ACID DISSOLVING PRODUCT | 2015 |
|
RU2607644C2 |
METHOD OF THE NATURAL URANIUM CHEMICAL CONCENTRATE PROCESSING | 2003 |
|
RU2315716C2 |
METHOD FOR PLUTONIUM RECOVERY FROM FIBERGLASS AEROSOL BORON- CONTAINING FILTER | 2003 |
|
RU2248324C1 |
URANIUM EXTRACTION AFFINAGE PROCESS | 2005 |
|
RU2295168C1 |
METHOD FOR EXTRACTING METALS OF PLATINUM GROUP FROM SEDIMENTS AFTER CLARIFYING ACID DISSOLUTION PRODUCT OF VOLOXIDISED SPENT NUCLEAR FUEL | 2016 |
|
RU2632498C2 |
PROCESSING METHOD OF URANIUM-BEARING MATERIALS | 2010 |
|
RU2422926C1 |
PROCEDURE FOR PROCESSING URANIUM ORE | 2010 |
|
RU2434961C1 |
METHOD FOR RECOVERING IRRADIATED NUCLEAR FUEL | 2005 |
|
RU2295167C1 |
METHOD FOR REGENERATING SPENT EXTRACTION SYSTEM BASED ON ORGANIC SOLUTION OF TRIBUTYL PHOSPHATE IN HEXACHLOROBUTADIENE (VARIANTS) | 2017 |
|
RU2648283C1 |
METHOD FOR RECOVERY OF SOLID AND/OR LIQUID URANIUM-CONTAINING WASTES | 2001 |
|
RU2200992C2 |
Authors
Dates
2012-07-20—Published
2010-08-30—Filed