Published November 1991
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Neutronic study using oxide and nitride fuels for the Super Phenix 2 reactor
Description
This report presents a neutronic analysis and a description of the Super Phenix 2 reactor, taken as reference. We present the methodology and results for cell and global reactor calculations for oxide (U O2- Pu O2) and nitride (U N - Pu N) fuels. To conclude we compare the performance of oxide and nitride fuels for the reference reactor. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
24002556.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Estudo neutronico e de desempenho de combustivel para o reator Super Phenix 2
Publishing Information
- Imprint Pagination
- 53 p.
- Report number
- IEN--32/91
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 24002556
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAST NEUTRONS; FUEL ELEMENTS; PLUTONIUM NITRIDES; SUPER PHENIX REACTOR; URANIUM DIOXIDE; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BARYONS; BREEDER REACTORS; CHALCOGENIDES; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; HADRONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NEUTRONS; NITRIDES; NITROGEN COMPOUNDS; NUCLEONS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM REACTORS; PNICTIDES; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES