2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025, pp.1802 - 1810
Abstract
Whole-core transient simulations with high-fidelity, pin-resolved details are vital for multi-physics reactor applications, driven by the increasing need for accuracy in nuclear reactor design. However, these simulations are computationally intensive. To overcome this challenge, a GPU-based Method of Characteristics (MOC) Transient Fixed Source Problem (TFSP) solver has been developed and incorporated into the STREAM Transient code, significantly enhancing the speed of neutron transient simulations. By leveraging GPUs' parallel processing capabilities, this approach substantially reduces the computational time for direct whole-core transport calculations. The GPU-optimized solver was validated using the C5G7-TD transport transient benchmark, its effectiveness in simulating heterogeneous problems, including both step and linear control rod movements. The demonstrating results show that the 2D transient transport solver performs well, with further optimization of time steps.