Published October 10, 2014 | Version v1
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Analysis of uncertainty propagation in nuclear fuel cycle scenarios

Description

Nuclear scenario studies model nuclear fleet over a given period. They enable the comparison of different options for the reactor fleet evolution, and the management of the future fuel cycle materials, from mining to disposal, based on criteria such as installed capacity per reactor technology, mass inventories and flows, in the fuel cycle and in the waste. Uncertainties associated with nuclear data and scenario parameters (fuel, reactors and facilities characteristics) propagate along the isotopic chains in depletion calculations, and through out the scenario history, which reduces the precision of the results. The aim of this work is to develop, implement and use a stochastic uncertainty propagation methodology adapted to scenario studies. The method chosen is based on development of depletion computation surrogate models, which reduce the scenario studies computation time, and whose parameters include perturbations of the depletion model; and fabrication of equivalence model which take into account cross-sections perturbations for computation of fresh fuel enrichment. Then the uncertainty propagation methodology is applied to different scenarios of interest, considering different options of evolution for the French PWR fleet with SFR deployment. (author)

Abstract (French)

Les etudes des scenarios electronucleaires modelisent le fonctionnement d'un parc nucleaire sur une periode de temps donnee. Elles permettent la comparaison de differentes options d'evolution du parc nucleaire et de gestion des matieres du cycle, depuis l'extraction du minerai jusqu'au stockage ultime des dechets, en se basant sur des criteres tels que les puissances installees par filiere, les inventaires et les flux, en cycle et aux dechets. Les incertitudes sur les donnees nucleaires et les hypotheses de scenarios (caracteristiques des combustibles, des reacteurs et des usines) se propagent le long des chaines isotopiques lors des calculs d'evolution et au cours de l'historique du scenario, limitant la precision des resultats obtenus. L'objet du present travail est de developper, implementer et utiliser une methodologie stochastique de propagation d'incertitudes dans les etudes de scenario. La methode retenue repose sur le developpement de metamodeles de calculs d'irradiation, permettant de diminuer le temps de calcul des etudes de scenarios et de prendre en compte des perturbations des parametres du calcul, et la fabrication de modeles d'equivalence permettant de tenir compte des perturbations des sections efficaces lors du calcul de teneur du combustible neuf. La methodologie de calcul de propagation d'incertitudes est ensuite appliquee a differents scenarios electronucleaires d'interet, considerant differentes options d'evolution du parc REP francais avec le deploiement de RNR

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Additional details

Additional titles

Original title (French)
Le cycle du combustible nucleaire et la prise en compte des incertitudes

Publishing Information

Imprint Pagination
352 p.
Report number
FRCEA-TH--7022

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
47056839
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Thesis
Descriptors DEI
COOLING; CROSS SECTIONS; DATA COVARIANCES; FUEL CYCLE; IRRADIATION; NUCLEAR FUELS; RADIOACTIVE WASTES
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; WASTES

Optional Information

Notes
52 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS-NKM website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/; Also available from http://sicd1.ujf-grenoble.fr/ (France)