Prediction of MgO volume fraction in an ADS fresh fuel for the scenario code CLASS. (November 2015)

• Record Type: Journal Article
• Authors: Thiollière, N.; Courtin, F.; Leniau, B.; Mouginot, B.; Doligez, X.; Bidaud, A.
• Is Part Of: Progress in nuclear energy. Volume 85(2015:Nov.)
• Page Start: 518
• Page End: 524
• Publication Date: 2015-11
• Subjects: ADS -- Minor actinides -- Plutonium -- Transmutation -- MgO inert matrix -- Neural network; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2015.05.011
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: Subcritical reactors, also called Accelerator Driven Systems (ADS), are specifically studied for their capacity in transmuting Minor Actinides (MA). Nuclear fuel cycle scenarios involving MA transmutation in ADS are widely researched. The nuclear fuel cycle simulation tool code CLASS (Core Library for Advanced Scenarios Simulations) is dedicated to the inventory evolution calculation induced by a complex nuclear fleet. For managing reactors, the code CLASS includes physic models. Loading models aim to provide the fuel composition at beginning of cycle according to the stocks isotopic composition and the reactors requirements. A cross section predictor aims to provide mean cross sections needed for solving Bateman equations. Physic models are built from reactors calculation set ahead of the scenario calculation. An ADS standard composition at BOC is a mixture of plutonium and MA oxide. The high number of fissile isotopes present in the subcritical core leads to an issue for building an ADS fuel loading model. A high number of isotopic vector at BOC is needed to get an exhaustive simulation set. Also, ADS initial reactivity is adjusted with an inert matrix which induces an additional degree of freedom. The building of an ADS fuel loading model for CLASS requires two steps. For any heavy nuclide composition at beginning of cycle, the core reactivity must be imposed at a subcritical level. Also, the reactivity coefficient evolution should be maintained during the irradiation. In this work, the MgO volume fraction is adjusted to reach the first requirement. The methodology based on a set of reactor simulations and neural network utilization to predict the MgO volume fraction needed to reach a wanted k eff for any initial composition is presented. Also, a complete neutronic study is done that highlight the effect on MgO on neutronic parameters. Reactor simulations are done with the transport code MCNP6 (Monte Carlo N particle transport code). The ADS geometry is based on the EFIT (European Facility for Industrial-Scale Transmutation) concept. The simulation set is composed of more than 8000 randomized runs from which a neural network has been built. The resulting MgO prediction method allows reaching a k eff at 0.96 and the distribution standard deviation is around 200 pcm. Highlights: We build an ADS databank from more than 8000 Monte Carlo simulations. MgO effect on neutron reactivity has been precisely assessed. MgO strongly affects the neutron flux and the cross sections. We analyse the simulation set with neural network. Reactivity is predicted precisely from any composition at B.O.C.