FIELD: power industry.
SUBSTANCE: invention can be used for re-processing of off-grade fuel assemblies of fuel elements and assemblies, which have gone through nuclear fuel cycle in the reactor. Dissolution of off-grade and spent nuclear fuel is characterised by use of water solution of ferrum salt as dissolution; at that, dissolution is carried out at pH 1.0-1.4, during 3-5 hours and molar ratio of fuel to ferrum salt equal to 1:2.1-2.5. As ferrum salt there used is ferric chloride or ferric nitrate.
EFFECT: achieving the best ecological, economical and social effects owing to eliminating the use of concentrated solutions of nitric acid, organic solvents and simplifying the further re-processing of spent fuel.
Title | Year | Author | Number |
---|---|---|---|
WASTE NUCLEAR FUEL PROCESSING METHOD | 2014 |
|
RU2560119C1 |
METHOD FOR DISSOLVING OFF-GRADE PELLETIZED PRODUCTS OF MOX-FUEL PRODUCTION | 2019 |
|
RU2704310C1 |
METHOD FOR EXTRACTION ISOLATION OF TRANSPLUTONIUM AND RARE EARTH ELEMENTS | 2021 |
|
RU2774155C1 |
METHOD OF PRODUCING SOLID PLUTONIUM DIOXIDE SOLUTION IN URANIUM DIOXIDE MATRIX | 2010 |
|
RU2446107C1 |
METOD OF PROCESSING SPENT NUCLEAR FUEL | 2008 |
|
RU2382425C1 |
METHOD FOR DISSOLVING SUBSTANDARD PRODUCTS OF MOX FUEL PRODUCTION | 2021 |
|
RU2754354C1 |
METHOD OF PREPARING SPENT CARBIDE NUCLEAR FUEL FOR EXTRACTION PROCESSING (VERSIONS) | 2013 |
|
RU2529185C1 |
METHOD OF PRODUCING SOLID PLUTONIUM DIOXIDE SOLUTION IN URANIUM DIOXIDE MATRIX | 2015 |
|
RU2598943C1 |
METHOD OF IRRADIATED NUCLEAR FUEL TREATMENT | 2007 |
|
RU2366012C2 |
METHOD OF PRODUCING SOLID PLUTONIUM DIOXIDE SOLUTION IN URANIUM DIOXIDE MATRIX | 2013 |
|
RU2554626C2 |
Authors
Dates
2010-09-27—Published
2009-07-02—Filed