Abstract
This paper presents the shielding analyses, which will be provided for supporting the design of the Test Cell Lithium System Interface Cell (TLIC) and safety assessment. The study considers the radiation decay source from IFMIF-DONES operation with beam-on. Radiation shielding simulations have been performed for the safety concerns. Detailed simulation geometry was created from CAD drawing for the TLIC. Neutron transport calculation was performed for all TLIC components concerned. The particle flux, biological dose and absorbed dose maps are provided in the study. A series of neutron transport are performed using the MCNP Monte Carlo McDeLicious neutron source code coupled with FISPACT for inventory calculations for TLIC design.
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