Speaker
Pedro Ortego
(Neutronic Calculations)
Description
In the conceptual design of the beam dump shielding for the foreseen fusion-relevant irradiation facility IFMIF, an inner lead cylinder performs the shielding of the highly activated copper cone undergoing the deuteron beam bombardment and low-alloy steel is used for front shielding. In order to reduce the residual dose around the beam dump at beam-off conditions and dose at hands-on operations, lead as an alternative material for the front shielding is considered.
The photon dose originated in the activation of the main components of such materials and of their impurities is calculated with the use of SEACAB system following the rigorous-two-step method (R2S) including the use of MCNPX code for neutron and photon transport and ACAB code for neutron activation. This methodology has been developed internally and benchmarked with the most accepted fusion-relevant benchmark for residual dose performed at Frascati Neutron Generator facility.
The source of secondary neutrons produced by the interaction of deuterons on the beam stopper has been calculated by the UNED team with the use of MCUNED and TALYS 1.0. The MCNPX input has been prepared starting from CAD files supplied by CIEMAT and translated to MCNP format with the use of MCAM interface developed by FDS team.
Co-authors
Alain Rodriguez
(Neutronic Calculations, SEA (Shielding Engineering and Analysis) SL, Las Rozas-Madrid, Spain)
Beatriz Branas
(National Fusion Lab., CIEMAT, Av. Complutense, Madrid, Spain)
Francisco Ogando
(TEC3FIR, UNED, Madrid, Spain)
Pedro Ortego
(Neutronic Calculations, SEA (Shielding Engineering and Analysis) SL, Las Rozas-Madrid, Spain)
