RU94037117A - Process of pyrochemical recovery of nuclear fuel - Google Patents
Process of pyrochemical recovery of nuclear fuelInfo
- Publication number
- RU94037117A RU94037117A RU94037117/25A RU94037117A RU94037117A RU 94037117 A RU94037117 A RU 94037117A RU 94037117/25 A RU94037117/25 A RU 94037117/25A RU 94037117 A RU94037117 A RU 94037117A RU 94037117 A RU94037117 A RU 94037117A
- Authority
- RU
- Russia
- Prior art keywords
- uranium
- fuel
- plutonium
- container
- electrolyte
- Prior art date
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Electrolytic Production Of Metals (AREA)
Abstract
FIELD: processing of irradiated and rejected nuclear fuel. SUBSTANCE: invention refers to processing of mononitride uranium-plutonium fuel. Nitride is loaded into container and electrolyte carrying not less than 15.0% of uranium thrichloride by mass is used. Electrolyte is heated to temperature not below 600 C and current having density not more than 0.3 A/sq.cm is created on container and not more than 0.4 A/sq.cm - on electrode. Current with density not more than 0.1 A/sq.cm is formed across fusible electrode. Melt is heated to temperature not higher than 700 C. Fusible metal or alloy which is more electrically positive than uranium nitride is also placed into container with nitride fuel. This metal alloy is solved in container and uranium and plutonium are precipitated on fusible electrode - cathode. EFFECT: decomposition of mononitride fuel and transition of uranium, plutonium and actinides in the form of chlorides into electrolyte, reduction and extraction of metallic uranium and plutonium, recovery of fission products from nuclear fuel.
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU94037117A RU2079909C1 (en) | 1994-09-27 | 1994-09-27 | Method of nuclear fuel pyrochemical regeneration |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU94037117A RU2079909C1 (en) | 1994-09-27 | 1994-09-27 | Method of nuclear fuel pyrochemical regeneration |
Publications (2)
Publication Number | Publication Date |
---|---|
RU2079909C1 RU2079909C1 (en) | 1997-05-20 |
RU94037117A true RU94037117A (en) | 1997-05-27 |
Family
ID=20161226
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
RU94037117A RU2079909C1 (en) | 1994-09-27 | 1994-09-27 | Method of nuclear fuel pyrochemical regeneration |
Country Status (1)
Country | Link |
---|---|
RU (1) | RU2079909C1 (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2562809C1 (en) * | 2014-05-30 | 2015-09-10 | Открытое акционерное общество "Новосибирский завод химконцентратов" (ОАО "НЗХК") | Method of regeneration of nuclear fuel powders from fuel elements and dispersion compositions based on aluminium and aluminium alloys |
RU2603844C1 (en) * | 2015-10-01 | 2016-12-10 | Федеральное государственное бюджетное учреждение науки Институт высокотемпературной электрохимии Уральского отделения Российской Академии наук | Method of nitride spent nuclear fuel recycling in salt melts |
US20200328004A1 (en) | 2017-12-29 | 2020-10-15 | State Atomic Energy Corporation "Rosatom" On Behalf Of The Russian Federation | Method of Reprocessing Nitride Spent Nuclear Fuel in Salt Melts |
RU2766563C2 (en) * | 2020-08-16 | 2022-03-15 | Акционерное общество «Прорыв» | Method of processing nitride snf in molten salt with extraction of the target component using a precipitator |
RU2758450C1 (en) * | 2020-08-16 | 2021-10-28 | Акционерное общество «Прорыв» | Method for processing nitride snf in salt melts with removal of the residual amount of the chlorinating agent |
-
1994
- 1994-09-27 RU RU94037117A patent/RU2079909C1/en active
Also Published As
Publication number | Publication date |
---|---|
RU2079909C1 (en) | 1997-05-20 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
HK4A | Changes in a published invention |