Spent fuel test on extraction in advanced reprocessing process
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Extraction tests of the 44,000MWd/t spent fuel dissolver solution using bench scale reprocessing experimental equipment at BECKY (Back-end Fuel Cycle Elements Research Facility) were carried out using three extractors. The equipment composed diluent washing, Np oxidation, co-extraction, FP scrubbing, Np separation, Tc separation, U/Pu partitioning and U recovery steps. Vanadium (V) oxide with nitric acid was used as an Np oxidizing agent. Butyraldehyde (decomposable and salt-free organic reducing agent) and 6M nitric acid were fed into the extractor in order to separate Np and Tc. As a result 64.8% of the Np and 98.9% of the Tc were extracted in the co-extraction step. 75.0% of the extracted Np was separated from the U and Pu stream in the Np separation step. On the other hand, 81.8% of the Tc was separated by 6M nitric acid in the Tc separation step. In the U/Pu partitioning step, Pu was reduced from Pu (IV) to Pu (III) and stripped into aqueous phase by uranous nitrate and hydrazine in 1M nitric acid. Most of the Np remained in the U loaded solvent (organic phase). To the contrary, Tc migrated to the Pu solution (aqueous phase). It was found that butyraldehyde and 6M nitric acid were effective in separating Np and Tc from the U and Pu stream. These technologies are expected to be applied to simplified reprocessing process. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international symposium NUCEF 2001. Scientific bases for criticality safety, separation process and waste disposal
- Imprint Pagination
- 735 p.
- Journal Page Range
- p. 489-495
- Report number
- JAERI-Conf--2002-004
Conference
- Title
- International symposium
- Acronym
- NUCEF 2001
- Dates
- 31 Oct - 2 Nov 2001
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37001956
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALDEHYDES; MODIFICATIONS; NEPTUNIUM 237; NITRIC ACID; PLUTONIUM RECYCLE; PUREX PROCESS; SOLVENT EXTRACTION; TECHNETIUM 99
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; EXTRACTION; FUEL CYCLE; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; NANOSECONDS LIVING RADIOISOTOPES; NEPTUNIUM ISOTOPES; NITROGEN COMPOUNDS; NUCLEI; ODD-EVEN NUCLEI; ORGANIC COMPOUNDS; OXYGEN COMPOUNDS; RADIOISOTOPES; REPROCESSING; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTOPES; TECHNETIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 6 refs., 9 figs., 2 tabs.; This record replaces 34002060