Phenix: Interpretation Of Ecrix-H Transmutation Experiment With Tripoli4D
Abstract
The ECRIX experiments aimed at demonstrating the transmutation capacity of sodium fast reactors regarding minor actinides (Americium, Neptunium, and Curium). These artificial atoms, produced in reactors, are mainly responsible for radiotoxicity and heat production of nuclear waste and thus concur to the complexity of storage facilities. Transmutation aims at reducing the amount of these products by irradiating them with neutron beams in dedicated facilities. The ECRIX-H experiment, performed from 2003 to 2006 in the French sodium cooled fast reactor Phenix, was focused on Americium transmutation in a softened neutron spectrum. The experimental pin was filled with a mixed material composed of americium oxide and magnesia. It was placed inside a calcium hydride container whose goal was to soften the neutron spectrum in order to enhance transmutation. Local neutron slowing-down due to hydrogen scattering reactions is a complex phenomenon which represents a challenge in terms of computer simulation. Previous interpretation campaigns highlighted limitations of standard fast reactor calculation schemes regarding both flux and depletion calculations with significant deviations (up to 50%). This paper will discuss of a new interpretation based on up-to-date calculation schemes using the stochastic transport calculation code TRIPOLI4D shipping a new depletion calculation module.
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