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First IFMIF/EVEDA Radioprotection Studies for the Preliminary Design of the Accelerator Beam Dump

J. Sanz, M. Garcia, F. Ogando, A. Mayoral, D. López, P. Sauvan, B. Brañas

Fusion Science and Technology

Volume 56 / Number 1 / July 2009 / Pages 273-280


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A preliminary beam dump cartridge design has been proposed recently for the IFMIF-EVEDA accelerator. Copper was the material chosen for the beam stop. In this paper we investigate the possibility of designing a practical shielding for the proposed cartridge so that it can offer an acceptable radioprotection response during both beam-on and beam-off phases. The radioprotection analysis is performed for the whole beam dump component located inside the already designed accelerator vault. A comprehensive methodology has been proposed to deal with the problem. Special attention has been paid to the treatment of the neutron source and a significant effort has been devoted to validation purposes. It is justified that prompt and residual dose rates can be provided with a reasonably conservative margin.

A base line shielding consisting of a 1 m water tank and a concrete shield of 1 m thickness in front of the tank can be a good approach to fulfill the radioprotection requirement assigned to the beam-on phase. This approach will not be acceptable for the beam-off but it is seen that a feasible solution can be reached by adding a plug at the entrance of the beam dump.

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