Experimental validation of the code system 'DARWIN' for spent fuel isotopic predictions in fuel cycle applications
Creators
- 1. CEA/DEN/DER/SPRC, CE Cadarache, F-13108 St Paul-Lez-Durance Cedex (France)
- 2. CEA/DEN/DM2S/Serma, CE Saclay, F-91191 Gif sur Yvette Cedex (France)
- 3. EDF, R and D, 1 av. General de Gaulle, F-92131 Clamart Cedex (France)
- 4. Areva/Cogema, 2 rue Paul Dautier, BP4, F-78141 Velizy Cedex (France)
- 5. Framatome, Tour Framatome, F-92084 Paris La Defense Cedex 16 (France)
Description
The DARWIN package, developed by the CEA and its French partners (Cogema, EDF and FRAMATOME) provides the required parameters in fuel cycle applications and characterizing the irradiated fuels from reactors: fuel inventory, decay heat, activity, neutron, γ, α, β sources and spectrum, radiotoxicity. In order to validate this code system for spent fuel inventory calculations, a large experimental programme has been performed in France, based on spent fuel chemical assays. Experimental data are based on chemical analysis measurements from fuel rod cuts irradiated in French PWR reactors and from full assembly dissolutions at the Cogema/La Hague reprocessing plants. This enables us to cover a large range of UOx fuels with various enrichments in 235U, 3.1% to 4.5%, associated with burnups from 10 GWd/t to 60 GWd/t. Recently, MOx fuels have also been investigated, with a initial Pu amount in the central zone of 5.6 % and a maximum burnup of 45 GWd/t. Uranium, Plutonium, Americium and Curium isotopes were analysed in PWR samples. Furthermore, Fission Products involved in Burn up Credit studies were measured. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 16 p.
Conference
- Title
- International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
- Acronym
- Physor 2002
- Dates
- 7-10 Oct 2002
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55004361
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AREVA NC LA HAGUE; BURNUP; CHEMICAL ANALYSIS; CURIUM ISOTOPES; FINANCIAL DATA; FISSION PRODUCTS; FRANCE; FUEL CYCLE; FUEL RODS; MIXED OXIDE FUELS; NUCLEAR INDUSTRY; PWR TYPE REACTORS; SPENT FUELS; URANIUM 235; VALIDATION
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AREVA NC; DATA; DEVELOPED COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EUROPE; EVEN-ODD NUCLEI; FRENCH ORGANIZATIONS; FUEL ELEMENTS; FUEL REPROCESSING PLANTS; FUELS; HEAVY NUCLEI; INDUSTRY; INFORMATION; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEI; NUMERICAL DATA; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; TESTING; THERMAL REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 18 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)