TY - GEN
T1 - Towards Control Drums Homogenization in Microreactors
T2 - 2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
AU - Abuzlf, Hadi
AU - Gilad, Erez
N1 - Publisher Copyright:
© 2025 AMERICAN NUCLEAR SOCIETY, INCORPORATED, WESTMONT, ILLINOIS 60559
PY - 2025/1/1
Y1 - 2025/1/1
N2 - In nuclear reactor design, particularly in the context of compact nuclear reactors, control drums play a key role in managing reactivity and ensuring operational safety and efficiency. This is exemplified in the Holos Gen-2+ design, which incorporates 20 control drums segmented into quadrants and positioned with azimuthal symmetry around the core's periphery. Each drum features a thin sector spanning 120°, composed of boron carbide (B4C), a neutron-absorbing material. The remaining portion of the drum is constructed from beryllium oxide (BeO). Given this design, the array of potential control drum configurations is virtually limitless. This study employs Monte Carlo simulations to investigate the characteristics of these diverse configurations, particularly when multiple control drums are involved. The findings of this study highlight the significant influence that interactions between adjacent control drums exert on their neutron-absorbing capacities, particularly through their relative and absolute rotational states. A significant aspect of this investigation is examining approaches to homogenize these configurations for employing multigroup nodal diffusion solvers. This is critical for simplifying the analysis and enabling more exhaustive searches in parameter space during a design process. It is shown that the homogenized absorption cross sections show highly irregular behavior as a function of the rotational state of adjacent drums. Moreover, it is shown that it is possible to obtain high accuracy in calculating the control drums configurations using multigroup nodal diffusion criticality calculations and homogenized cross sections.
AB - In nuclear reactor design, particularly in the context of compact nuclear reactors, control drums play a key role in managing reactivity and ensuring operational safety and efficiency. This is exemplified in the Holos Gen-2+ design, which incorporates 20 control drums segmented into quadrants and positioned with azimuthal symmetry around the core's periphery. Each drum features a thin sector spanning 120°, composed of boron carbide (B4C), a neutron-absorbing material. The remaining portion of the drum is constructed from beryllium oxide (BeO). Given this design, the array of potential control drum configurations is virtually limitless. This study employs Monte Carlo simulations to investigate the characteristics of these diverse configurations, particularly when multiple control drums are involved. The findings of this study highlight the significant influence that interactions between adjacent control drums exert on their neutron-absorbing capacities, particularly through their relative and absolute rotational states. A significant aspect of this investigation is examining approaches to homogenize these configurations for employing multigroup nodal diffusion solvers. This is critical for simplifying the analysis and enabling more exhaustive searches in parameter space during a design process. It is shown that the homogenized absorption cross sections show highly irregular behavior as a function of the rotational state of adjacent drums. Moreover, it is shown that it is possible to obtain high accuracy in calculating the control drums configurations using multigroup nodal diffusion criticality calculations and homogenized cross sections.
KW - DYN3D
KW - HOLOS microreactor
KW - homogenized cross-sections
KW - rotating control drums
UR - https://www.scopus.com/pages/publications/105010193084
U2 - 10.13182/MC25-47156
DO - 10.13182/MC25-47156
M3 - Conference contribution
AN - SCOPUS:105010193084
T3 - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
SP - 482
EP - 490
BT - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PB - American Nuclear Society
Y2 - 27 April 2025 through 30 April 2025
ER -