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Insight into the materials choice for inertial fusion energy reactors considering radiation damage: Neutron irradiation intensities and basic knowledge from multiscale modeling

  • J.M. PERLADO (a1), E. DOMÍNGUEZ (a1), D. LODI (a1) (a2), J. MARIAN (a1) (a3), M. SALVADOR (a1), J. SANZ (a1), A.I. GONZÁLEZ (a1), M.J. CATURLA (a3), T. DÍAZ DE LA RUBIA (a3), B.D. WIRTH (a3) and L. COLOMBO (a4)...


A review of structural materials choices under irradiation in fusion environments is presented. Results on the neutron source term and the intensities in the structural materials as a function of pulse time, energy, and protection is given. The role of multiscale modeling for understanding the basic physics in irradiated materials is explained, and simulations of metals under pulse irradiation and SiC are reported.


Corresponding author

Address correspondence and reprint requests to: J.M. Perlado, Instituto de Fusión Nuclear (DENIM), Universidad Politécnica de Madrid (UPM) E.T.S.I.I., J. Gutiérrez Abascal, 2; 28006 Madrid, Spain. E-mail:



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