Development of the ERIX process for reprocessing spent FBR-MOX fuel. A hot test on U and Pu recovery and the process improvement
- 1. Institute of Research and Innovation (IRI), Kashiwa, Chiba (Japan)
Description
To develop an advanced technology for reprocessing spent FBR-MOX fuel, we have been studying a new aqueous reprocessing system named ERIX Process. This process consists of (1) Pd removal by selective adsorption; (2) electrolytic reduction for the valence adjustment of U, Pu, Np. Ru and Tc; (3) anion exchange separation of U, Pu and Np; and (4) selective separation of MA (Am, Cm) by extraction chromatography. In this work, hot tests of electro-reduction using a flow type electrolysis cell and anion exchange separation by AR-01 packed column for the recovery of U and Pu from an irradiated MOX-fuel solution were carried out according to the main process of the ERIX flowsheet. All of the FPs and MA showed no adsorption and leaked from the column firstly. In the electrolysis, U and Np were effectively reduced to U(IV) and Np(IV) and separated completely from the FPs. On the other hand, a part of Pu was reduced to Pu(III) which mixed with FPs in column separation. To achieve a successful separation of Pu from FPs, the ERIX process was improved by adopting an additional anion exchange column to recover Pu(IV) prior to the electro-reduction of U(VI). (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37056268
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANIONS; ELECTROLYSIS; EXTRACTION CHROMATOGRAPHY; FBR TYPE REACTORS; FISSION PRODUCTS; ION EXCHANGE; MATERIALS RECOVERY; MIXED OXIDE FUELS; PLUTONIUM; REPROCESSING; SPENT FUELS; URANIUM
- Descriptors DEC
- ACTINIDES; BREEDER REACTORS; CHARGED PARTICLES; CHROMATOGRAPHY; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; IONS; ISOTOPES; LYSIS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; PROCESSING; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL0XX, Paper ID GL032DF.pdf; 17 refs., 7 figs., 3 tabs.