# 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.

## Contents

```{toctree}
:maxdepth: 2

intro
quickstart
specifications/index
benchmark_collection/index
```