https://doi.org/10.1051/epjconf/202430213003
Preliminary analysis of TREAT free-field experiments using OpenMC
1 Fuel Development, Performance & Qualification, Idaho National Laboratory, 1955 N Fremont Ave, Idaho Falls, ID 83415
2 Radiochemistry & Nuclear Measurements, Idaho National Laboratory, 1955 N Fremont Ave, Idaho Falls, ID 83415
3 Irradiation Experiment Neutronics Analysis, Idaho National Laboratory, 1955 N Fremont Ave, Idaho Falls, ID 83415
* e-mail: paul.ferney@inl.gov
Published online: 15 October 2024
This work analyses activation calculations for dosimetry materials during a steady-state irradiation in the Transient Reactor Test (TREAT) reactor core. Hence, we developed a workflow based on the Monte Carlo code OpenMC alongside a custom depletion solver. The irradiation-induced activity as a function of time is computed, and several sensitivity studies are performed to evaluate uncertainty. This study has shown activity computations are sensitive to flux amplitude, irradiation time, atoms quantity and microscopic cross sections. Stochastic uncertainties have been propagated to evaluate the activity uncertainty for each dosimetry material. Most uncertainties are below our target of 3%, which demonstrates OpenMC as a powerful predictive and analysis tool. The precise results obtained through this newly developed computation scheme will be used in future experiments to characterize quantities of interest when operating the TREAT reactor in new configurations.
© The Authors, published by EDP Sciences, 2024
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
