Validation Dataset for VERA Benchmark Problems 6 and 7 Based on the OpenMC/COBRA-EN Coupled Code

This dataset originates from the research paper “Research on a Coupled Neutronics/Thermal-Hydraulics Calculation Method for PWRs Based on OpenMC/COBRA-EN”. The study developed a neutronics/thermal-hydraulics (N/TH) coupling code based on the open-source Monte Carlo code OpenMC and the subchannel code COBRA-EN. To validate the code, high-fidelity simulations were performed on the internationally recognized VERA (Virtual Environment for Reactor Applications) Benchmark Problems 6 (single assembly) and 7 (full core). The dataset contains key output results from the coupled code upon steady-state convergence, including: the effective multiplication factor (keff), fuel pin and assembly power distributions, fuel temperature distribution, coolant outlet temperature and density distributions, and the critical boron concentration. This dataset can be used to verify the accuracy of other multi-physics coupling codes and serves as a reference for high-fidelity reactor simulations.