Cesar: a simplified evolution code for reprocessing applications
- 1. CEA/Cadarache, Direction des Reacteurs Nucleaires, DRN/DER, 13 - Saint-Paul-lez-Durance (France)
- 2. Cogema la Hague, 50 - Beaumont Hague (France)
- 3. CEA Cadarache, CISI DOP, 13 - Saint Paul lez Durance (France)
Description
In the framework of a collaboration between CEA and COGEMA, CESAR has been developed to provide the required characterization data for burn up fuels from PWRs. BWRs and FRs. It can quickly calculate the evolution, in and out of pile, of material balances, and the activity, decay heat and neutron source emitted by the irradiated fuel, taking into account 104 actinides, 208 fission products and 125 activation products. CESAR can also make flux depletion calculations of radioactive sources, up to geological times (106 years). The neutronics data libraries (cross sections sets) are supplied by the CEA reference calculation codes for neutron physics: APOLLO for thermal spectrum systems and ERANOS for fast spectrum systems. In the near future, they will be supplied by the DARWIN package. For the principal nuclides, the code has been validated using two types of experimental results: isotopic analysis from burn up fuel rod samples and also from full assemblies dissolutions from the reprocessing plants. (author)
Additional details
Publishing Information
- Publisher
- Societe francaise d'energie nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- Nuclear recycling. RECOD 98. 5. international nuclear conference on recycling, conditioning and disposal
- Imprint Pagination
- [1100 p.]
- Journal Page Range
- p. 986-993
Conference
- Title
- RECOD 98. 5. international conference on recycling, conditioning and disposal
- Dates
- 25-28 Oct 1998
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 32043433
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; BURNUP; BWR TYPE REACTORS; C CODES; FAST REACTORS; FISSION PRODUCTS; FUEL RODS; PWR TYPE REACTORS; SPENT FUELS
- Descriptors DEC
- COMPUTER CODES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FUEL ELEMENTS; FUELS; ISOTOPES; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS