Now showing items 1-2 of 2

    • Monte Carlo simulations of the n TOF lead spallation target with the Geant4 toolkit: A benchmark study 

      Lerendegui-Marco, J.; Cortés-Giraldo, M.A.; Guerrero Sánchez, Carlos; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere (EDP Sciences, 2016)
      Conference lecture
      Open Access
      Monte Carlo (MC) simulations are an essential tool to determine fundamental features of a neutron beam, such as the neutron flux or the ¿ -ray background, that sometimes can not be measured or at least not in every position ...
    • New measurement of the 242Pu(n,gamma) cross section at n TOF-EAR1 for MOX fuels: Preliminary results in the RRR 

      Lerendegui-Marco, J.; Guerrero, C.; Cortés-Giraldo, M.A.; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Tarifeño Saldivia, Ariel Esteban (EDP Sciences, 2016)
      Conference lecture
      Open Access
      The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing ...