Method of recovering neptunium from spent nuclear fuel. [an improved Purex wet recovery process]
An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous acid by using a multistage extractor unit having an extracting section and a washing section is provided for separating and recovering neptunium simultaneously with uranium and plutonium contained in spent nuclear fuel. The improved method comprises the steps of maintaining the nitrous acid concentration in said extracting section at a level suited for effecting oxidation of neptunium from (V) to (VI) valence, while lowering the nitrous acid concentration in said washing section so as to suppress reduction of neptunium from (VI) to (V) valence, and maintaining the nitric acid concentration in said washing section at a high level.
- Assignee:
- Doryokuro Kakunenryo Kaihatsu Jigyodan
- Patent Number(s):
- US 3962401
- OSTI ID:
- 7272019
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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ACTINIDES
BUTYL PHOSPHATES
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
METALS
NEPTUNIUM
NITROUS ACID
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
PLUTONIUM
PUREX PROCESS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPENT FUELS
TBP
TRANSURANIUM ELEMENTS
URANIUM
VALENCE