Application of gel-Co-conversion for TRU (Pu, Np, Am) fuel and target preparation
Creators
- 1. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d'Etudes des Combustibles
- 2. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Description
In the fabrication of fuel containing transuranium (TRU) elements, flow sheets and techniques which allow a shielded and/or remote fabrication will probably need to be applied. One approach, which has been demonstrated on the laboratory and semi prototype scale, is the wet fabrication route of coprecipitation of the matrix element uranium mixed with plutonium to form dense spherical particles or to produce hybrid pellets made from pressed gel microspheres. The ceramic material produced holds the TRU-elements homogeneously distributed in the matrix. In conjunction with the Departement d'Etudes des Combustibles of the French Commissariat a l'Energie Atomique (CEA-DEC) in Cadarache, the Paul Scherrer Institut (PSI) in Switzerland is further developing a mixed nitride ceramic and mixed oxide with high concentrations (up to 50%) of plutonium with the aim of a joint irradiation test of transuranium elements in the French PHENIX reactor. 6 refs., 3 figs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number.Files
25003379.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- CEA-CONF--11608
Conference
- Title
- future nuclear systems - emerging fuel cycles and waste disposal options.
- Acronym
- Global '93
- Dates
- 12-17 Sep 1993.
- Place
- Seattle, WA (United States).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 25003379
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACTINIDES; CEA CADARACHE; COORDINATED RESEARCH PROGRAMS; COPRECIPITATION; EXPERIMENTAL DATA; FUEL PELLETS; GELATION; MIXED NITRIDE FUELS; PHENIX REACTOR; PLUTONIUM NITRIDES; SINTERED MATERIALS
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; CEA; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FBR TYPE REACTORS; FRENCH ORGANIZATIONS; FUELS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; NUMERICAL DATA; PLUTONIUM COMPOUNDS; PLUTONIUM REACTORS; PNICTIDES; POWER REACTORS; PRECIPITATION; REACTOR MATERIALS; REACTORS; RESEARCH PROGRAMS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; SOLID FUELS; TRANSURANIUM COMPOUNDS