Application with COSI code of gen IV fast reactors introduction in the French park
- CEA Cadarache, DER/SPRC B 230, 13108 St Paul lez Durance (France)
- CEA Saclay, DEN/DDIN B 121, 91191 Gif/Yvette (France)
The insertion of a new concept (fuel, reactor, process) must be evaluated in the global electronuclear system with an analysis of the impact on the fuel cycle (Enrichment, Fuel Fabrication, Reactor, Processing, Interim Storage, Waste storage). An approach of scenario studies is used to evaluate different solutions to manage nuclear materials (uranium, plutonium) and wastes (minor actinides and fission products), from the present situation (partially closed cycle) until the total closed cycle with GEN IV systems, in calculating the fluxes and the inventories of these elements in each step of the fuel cycle and to treat the transient period to pass from one situation to the others. For some interesting scenarios, the approach consists on a simulation of transient scenarios from the present situation to the equilibrium situation with a COSI code. The results given at each point of the fuel cycle and for each year permit to demonstrate the technological feasibility and to evaluate the impacts on environmental, economical, proliferation and waste storage aspects. After a presentation of the operational approach, this paper gives an example for a French transient scenario between the present situation and the end of the 21. century with the introduction of GEN IV fast reactors. The results presented in this paper give the impacts on: - The natural uranium resources, - The capacity of different plants (enrichment, fabrication, reprocessing) and interim storages for spent fuels, - The inventory, function of time, of different elements (Pu, Np, Am, Cm) at each stage of the fuel cycle and in the wastes, - The thermal power the high level wastes. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979733
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 5 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTER CODES
FAST REACTORS
FEED MATERIALS PLANTS
FUEL CYCLE
FUEL FABRICATION PLANTS
FUEL REPROCESSING PLANTS
HIGH-LEVEL RADIOACTIVE WASTES
ISOTOPE SEPARATION PLANTS
NATURAL URANIUM
PLUTONIUM
PROLIFERATION
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE STORAGE
REPROCESSING
SPENT FUELS
URANIUM DEPOSITS