%0 Conference Paper %F Oral %T Nuclear data propagation with burnup : impact on SFR reactivity coefficients %+ CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)) %A Buiron, Laurent %A Plisson-Rieunier, Danièle %< avec comité de lecture %B ICAPP17 %C Fukui-Kyoto, Japan %8 2017-04-24 %D 2017 %K SFR %K sesnibilites en evolution %K uncertitudes %K COMAC %Z Physics [physics]/Nuclear Experiment [nucl-ex] %Z Physics [physics]/Nuclear Theory [nucl-th]Conference papers %X For the next generation fast reactor design, theGeneration IV International Forum (GIF) defined globalobjectives in terms of safety improvement, sustainability,waste minimization and non-proliferation. Among thepossibilities studied at CEA, Sodium cooled Fast Reactor(SFR) are studied as potential industrial tools for nextdecade’s deployment. Many efforts have been made in thelast years to obtain advanced industrial core designs thatcomply with these goals. Concerning safety issues,particular efforts have been made in order to obtain coredesigns that can be resilient to accidental transients. The“safety” level of such new designs is often characterizedby their “natural” behavior under unprotected transientssuch as loss of flow or hypothetical transient over power.Transient analysis needs several accurate neutronic inputdata such as reactivity coefficient and kinetic parameters.Beside estimation of the level of “absolute” values,associated uncertainties have also to be evaluated for thewhole set of relevant data. These estimations have to beperformed for different core state such as end of cyclecore for feedback coefficient. This means thatuncertainties have to be obtained not only a fixed time butalso have to be propagated all through irradiation.To do so, we need to couple Boltzman and Batemanequations at sensitivities level. The coupling processcould be done with the help of the perturbation theorywhich gives adapted framework suited for deterministiccalculation codes. This coupling is currently in progressin ERANOS code system. The actual implementation givesaccess to estimation of sensitivities for both reactivitycoefficients and mass balance.After a brief theoretical description of Boltzman/Batemancoupling capabilities in ERANOS, the study presented inthis paper focuses on sensitivity and uncertaintiesestimation for the main feedback coefficients involved infast reactor transients: the thermal sodium expansioncoefficient and the Doppler Effect. Using thesesensitivities, a global evaluation of impact of the fueldepletion can be quantified for these reactivity effects atcore scale for end of cycle state. An illustration is givenfor a GEN IV SFR industrial core design (SFR V2B). Afirst glance at preliminary uncertainty level is presentedusing current covariance matrices available at CEA. %G English %2 https://cea.hal.science/cea-02435062/document %2 https://cea.hal.science/cea-02435062/file/201600003885.pdf %L cea-02435062 %U https://cea.hal.science/cea-02435062 %~ CEA %~ DEN