Conférences et séminaires » Séminaire présenté par B. Mouginot, SUBATECH, Nantes

Séminaire présenté par B. Mouginot, SUBATECH, Nantes

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CLASS : the electronuclear software for in2p3, First application on the French electronuclear fleet.

Par : Baptiste Mouginot, Subatech Laboratory, EMN, Université de Nantes, CNRS
Date : vendredi 3 mai 2013 à 10h30
Lieu : IPHC, Salle de Réunion 2e étage du Bâtiment 27

Résumé :

The nuclear reactor simulation community has a requirement to perform complex electronuclear scenario simulation. To avoid constraints coming from existing powerful scenario software as COSI, VISION or FAMILY, the open source Core Library for Advance Scenario Simulation (CLASS) is being developed.

CLASS main asset is its ability to include any kind of reactor, whether the system is innovative or standard. A reactor is fully described by its evolution database that should contain a set of different validated fuel compositions in order to simulate transitional scenarios. CLASS aims to be a useful tool to study scenarios involving Generation IV reactors as well as innovative fuel cycles, like the Thorium cycle.

In addition of all standard key objects required by an electronuclear scenario simulation (the isotopic vector the reactor, the fuel storage and the fabrication units), is also integrated in CLASS two specific modules : one dealing the fabrication of recycled fuel (according to user priority/algorithm). The second module is dealing the fresh fuel evolution by solving Bateman equations built with database induced cross-sections. By default, the fuel fabrication (for a recycled one) uses a “linear Pu equivalent“ method [1], which allows predicting, from the isotopic composition, the maximum burn-up accessible for a set type of fuel.

The following contribution presents the basis of a CLASS scenario, the fuel method apply to a MOX Fuel and a benchmark of the evolution modules, illustrated on a scenario based on a the French electronuclear fleet from 1977 to 2012.

Personne à contacter : Kamila SIEJA


[1Performance of Pu/Th fuels in PWR, analysis of the fissile material effiency for future reactors. G.Kepisty, S.David, Internship report, Institut de Physique Nucléaire d’Orsay – CNRS.