FIELD: radiochemical technology.
SUBSTANCE: invention relates to radiochemical technology, in particular to methods for separating neptunium and plutonium by extraction methods during the processing of spent nuclear fuel. The method includes the treatment of the initial solution containing plutonium, neptunium with a reducing reagent, which restores plutonium to the trivalent state, and neptunium to the tetravalent state. A carbohydrazide solution with a concentration of 0.3 mol/l or higher is used as a reducing reagent. The duration of exposure of the solution for the reduction of Np(VI) to Np(IV) before the start of the extraction separation process is 270-300 minutes at a temperature of 66°C.
EFFECT: invention makes it possible to simplify and improve the safety of the process of separating neptunium from plutonium in refining operations of spent nuclear fuel reprocessing technology.
5 cl, 2 dwg, 3 tbl
| Title | Year | Author | Number |
|---|---|---|---|
| IRRADIATED NUCLEAR FUEL EXTRACTION PROCESSING METHOD | 2020 |
|
RU2727140C1 |
| METHOD OF EXTRACTION AND SEPARATION OF PLUTONIUM AND NEPTUNIUM | 2015 |
|
RU2642851C2 |
| PROCESSING METHOD OF NITRIC-ACID SOLUTION OF REGENERATED URANIUM WITH REMOVAL OF TECHNETIUM (VERSIONS) | 2009 |
|
RU2430175C1 |
| METHOD OF PROCESSING NITRATE SOLUTION OF RECOVERED URANIUM COMBINED WITH REMOVAL OF TECHNETIUM | 2011 |
|
RU2490210C1 |
| METHOD FOR EXTRACTION PURIFICATION OF URANIUM EXTRACT FROM TECHNETIUM | 2021 |
|
RU2767931C1 |
| METHOD FOR NEPTUNIUM REMOVAL DURING SEPARATION OF LONG-LIVING RADIONUCLIDES | 2010 |
|
RU2454740C1 |
| APP IRRADIATED FUEL PROCESSING METHOD | 2013 |
|
RU2535332C2 |
| PROCESSING METHOD OF IRRADIATED NUCLEAR FUEL OF NUCLEAR POWER PLANTS | 2010 |
|
RU2454741C1 |
| METHOD OF PROCESSING OF IRRADIATED FUEL OF ATOMIC POWER PLANTS | 1992 |
|
RU2012075C1 |
| METHOD FOR TREATMENT OF REPROCESSED URANIUM | 2010 |
|
RU2447523C2 |
