Performance assessment of nuclear fuel cycles dedicated to uranium and plutonium multi-recycling
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hdl:2117/344712
Realitzat a/ambInnoEnergy; École nationale supérieure de chimie de Paris; Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
Tipus de documentProjecte Final de Màster Oficial
Data2020-01-10
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Reconeixement-NoComercial-CompartirIgual 3.0 Espanya
Abstract
In light of the recent postponement of the deployment of commercial Sodium Fast Reactors in France to at least the second half of the 21st century, multi-recycling of plutonium and uranium in PWRs has become an attractive option for better ssile material and natural resource management. The implications for cycle facilities and waste management, that these advanced material management options entail, need to be carefully studied and can be used to compare the diferent options. The newly developed equilibrium scenario code SEPAR (Simulateur d'Equilibres de Parcs Avancés de Réacteurs) is used to simulate equilibrium PWR fl eets dedicated to multi-recycling of uranium and plutonium. The functionality of the code was tested on mono-recycling cycles, after which partial multi-recycling and full multi-recycling cycles, using the MIX fuel concept, were modelled. Post-processing routines were developed to extract the results from SEPAR and calculate values of interest such as isotopic compositions, fuel fabrication needs and natural uranium consumption. A method to calculate the production of plutonium and minor actinides, associated to the modelled cycle options, was devised and is described. It was found that recycling fissile material allows to reduce natural uranium consumption, but generally increases the minor actinide production. Reactors fuelled by plutonium-based fuels are shown to increase the production of americium and curium, while using fuels based on reprocessed and re-enriched uranium increases the neptunium production of the fl eet. If plutonium is recycled, the fl eet composition and the production of plutonium and minor actinides are strongly dependent on cooling and fabrication times of the fuels. An increase of the minor actinide production with longer cooling and fabrication times is found for these fl eets, with the effect being largest for full multi-recycling fl eets. The isotopic compositions of fuels found for the full multi-recycling scenarios confi rm that new cycle facilities, such as reprocessing and plutonium-based fuel fabrication facilities, are needed to achieve the advanced scenarios. The code was found to perform well and obtained results are promising, although not validated yet. Future work will include validating the results and including the post-processing methods directly in the SEPAR code. Sensitivity studies on the advanced cycles as well as simulating other advanced cycles, including diferent systems, such as fast reactors or transmutation systems, can be performed. Some minor improvements to the code, such as extending the list of considered elements and isotopes, are also possible.
MatèriesNuclear fuels -- Analysis, Pressurized water reactors -- Cores -- Computer simulation, Nuclear power plants -- France -- Management, Combustibles nuclears -- Anàlisi, Reactors nuclears d'aigua a pressió -- Control -- Mètodes de simulació, Centrals nuclears -- Optimització -- França
TitulacióMÀSTER UNIVERSITARI EN ENGINYERIA NUCLEAR (Pla 2012)
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thesis.pdf | 2,868Mb | Visualitza/Obre |