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Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources

We propose here to implement an optimization methodology of the blankets design with regards to various parameters such as the local spectrum or the mass to be loaded, with the objective of minimizing the final neutron source of the spent assembly while maximizing the transmutation performances of the blankets. | Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources EPJ Nuclear Sci. Technol. 3 7 2017 Nuclear Sciences T. Kooyman et al. published by EDP Sciences 2017 amp Technologies DOI 10.1051 epjn 2017003 Available online at http www.epj-n.org REGULAR ARTICLE Analysis and optimization of minor actinides transmutation blankets with regards to neutron and gamma sources Timothée Kooyman1 Laurent Buiron1 and Gérald Rimpault2 1 DEN DER SPRC LEDC CEA Cadarache 13108 Saint Paul lez Durance France 2 DEN DER SPRC LEPh CEA Cadarache 13108 Saint Paul lez Durance France Received 24 October 2016 Received in final form 18 January 2017 Accepted 25 January 2017 Abstract. Heterogeneous loading of minor actinides in radial blankets is a potential solution to implement minor actinides transmutation in fast reactors. However to compensate for the lower flux level experienced by the blankets the fraction of minor actinides to be loaded in the blankets must be increased to maintain acceptable performances. This severely increases the decay heat and neutron source of the blanket assemblies both before and after irradiation by more than an order of magnitude in the case of neutron source for instance. We propose here to implement an optimization methodology of the blankets design with regards to various parameters such as the local spectrum or the mass to be loaded with the objective of minimizing the final neutron source of the spent assembly while maximizing the transmutation performances of the blankets. In a first stage an analysis of the various contributors to long- and short-term neutron and gamma source is carried out whereas in a second stage relevant estimators are designed for use in the effective optimization process which is done in the last step. A comparison with core calculations is finally done for completeness and validation purposes. It is found that the use of a moderated spectrum in the blankets can be beneficial in terms of