Published 1994
| Version v1
Miscellaneous
Treatment of nuclear spent fuel for advanced cycles
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
Description
Studies on the treatment of spent nuclear fuel for MOX fuel fabrication at advanced cycles is presented. A modified Purex process, employing the electrolytic mixer-settler MIRELE, developed at IPEN-CNEN/SP, in the U-Pu stripping to the aqueous phase and recovery of Pu traces from organic phase, was studied. The obtained results have demonstrated the viability of using the proposed flowsheet in the nuclear fuel recycling. (author). 9 refs, 10 figs
Additional details
Additional titles
- Original title (Portuguese)
- Tratamento do combustivel nuclear irradiado para ciclos avancados
Publishing Information
- Imprint Title
- Proceedings of the 5. General Congress on Nuclear Energy. v. 2
- Imprint Pagination
- 356 p.
- Journal Page Range
- p. 561-565.
Conference
- Title
- 5. General Congress on Nuclear Energy.
- Dates
- 28 Aug - 2 Sep 1994.
- Place
- Rio de Janeiro, RJ (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 26041474
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FBR TYPE REACTORS; FUEL CYCLE; MIXED OXIDE FUELS; MIXER-SETTLERS; NUCLEAR FUELS; POWER REACTORS; PUREX PROCESS; SOLVENT EXTRACTION
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; EQUIPMENT; EXTRACTION; EXTRACTION APPARATUSES; FAST REACTORS; FUELS; MATERIALS; REACTOR MATERIALS; REACTORS; REPROCESSING; SEPARATION EQUIPMENT; SEPARATION PROCESSES; SOLID FUELS
Optional Information
- Notes
- Imprint:Anais do 5. Congresso Geral de Energia Nuclear. v. 2.