Speaker
Description
Tritium production in particle accelerator facilities must be carefully evaluated to ensure safe operation and compliance with regulatory limits. Radiation transport codes can estimate tritium production in accelerator components and shielding; however, they generally do not describe the subsequent release of tritium or its diffusion through shielding materials.
This work presents an integrated approach that combines radiation transport calculations with experimental measurements. The Monte-Carlo codes CERN-FLUKA and PHITS are used to design and optimize the planned experimental setup in which various materials are irradiated by secondary particles generated from proton beam interaction with a target. These irradiated materials would then be submerged in water for a specified period, after which the tritium concentration in the water would be measured. These experimental results will provide estimates of tritium release from irradiated materials and support the development of improved models for tritium transport, as well as environmental release in accelerator facilities; this will help expand the tools available for tritium management and safety assessment in the accelerator community.
| Topics | T5. Induced radioactivity and decommissioning |
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