OpenMC Fusion Benchmarks#
Welcome to the OpenMC Fusion Benchmarks project - a modular, code-agnostic, and automation-ready repository for defining, executing, and analyzing radiation transport benchmarks in fusion energy systems. Benchmarks are described through a rigorous, schema-driven YAML specification, and include detailed CAD-based geometries with automatic meshing support. The framework is designed for easy integration and testing of new neutronics methods, facilitating rapid development, comparison, and validation across codes, workflows, and datasets.