Concept and experimental studies on fuel and target for minor actinides and fission products transmutation
- 1. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d'Etudes des Combustibles
- 2. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Direction des Reacteurs Nucleaires
- 3. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d'Etudes des Reacteurs
Description
High activity long-lived radionuclides in nuclear wastes, namely minor actinides (americium and neptunium) are in large amount generated by current nuclear reactive. The destruction of these radionuclides is a part of the French SPIN (Partitioning and Burning) program consistent with the determination to send a minimum amount of harmful products for final storage. Transmutation concepts are defined for neptunium and americium taking into account fuel cycle strategies. Neptunium destruction does not pose any major problems. It's a by-product of uranium consumption, as plutonium and in despite of a slight gamma activity due to the protactinium 233 it's quite easy to handle. Diluting neptunium in the mixed oxide fuels (MOX) should not be an obstacle for fabrication, in-pile behaviour and reprocessing either. Consequently we make the proposal of homogeneous mode of neptunium in MOX which should be soon explored in the experimental OSIRIS reactor and in the Phenix and Superphenix reactors. The analysis is more complex for the multi isotope americium. Its destruction is difficult because of gamma radioactivity which complicates fabrication. Experiments in Phenix and calculation showed that Phenix reactor offers a good potential for americium incineration, but similar data do not exist for PWR. It will remain a well known difficulty for fabrication and reprocessing. In this case we have to put a real new face to the fabrication flow-sheet of americium compounds and we propose to develop the heterogeneous mode. Targets choice are defined in term of: -safety, considering fuel reaction with cladding and water sodium, -transmutation rate, limited by target behaviour, in FR's (Phenix), PWR's (OSIRIS) and HFR (Petten), -reprocessing, checking the solubility of such targets by Purex process. So, at the beginning of our program the account has been on improving fuel and targets properties related to safety and fuel cycle. (authors). 4 figs
Availability note (English)
MF available from INIS under the Report Number.Files
27048526.pdf
Files
(144.7 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:6005134d491ba630400dd31838070530
|
144.7 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CEA-CONF--12296
Conference
- Title
- 3. NEA International Information Exchange Meeting.
- Dates
- 12-14 Dec 1994.
- Place
- Cadarache (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 27048526
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMERICIUM; FISSION PRODUCTS; HFR REACTOR; MIXED OXIDE FUELS; NEPTUNIUM; OSIRIS REACTOR; PHENIX REACTOR; PROTACTINIUM 233; PUREX PROCESS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RECYCLING; REPROCESSING; SPENT FUELS; SUPER PHENIX REACTOR; TRANSMUTATION
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BREEDER REACTORS; DAYS LIVING RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; HEAVY NUCLEI; IRRADIATION REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MANAGEMENT; MATERIALS; MATERIALS TESTING REACTORS; METALS; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; PLUTONIUM REACTORS; POWER REACTORS; PROTACTINIUM ISOTOPES; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEPARATION PROCESSES; SODIUM COOLED REACTORS; SOLID FUELS; STORAGE; TANK TYPE REACTORS; THERMAL REACTORS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS