Input Files for "Extending OpenMC Validation to Spent Fuel Canisters: A Criticality Benchmark Against MCNP"

This dataset contains OpenMC and MCNP input files for one of the benchmark cases presented in the article *"Extending OpenMC Validation to Spent Fuel Canisters: A Criticality Benchmark Against MCNP"*. The selected case represents the 'Normal operation' configuration, which locates a spent nuclear fuel canister in a borehole within a tunnel, based on the KBS-3 concept.

The objective of this release is to support reproducibility and encourage transparent research in neutron transport simulations applied to radioactive waste management.

The files were originally prepared by Javier Ruiz-Pineda as part of his undergraduate thesis research. Jaime Romero-Barrientos, his academic advisor, is the corresponding author of the associated article. Both authors are affiliated with the Chilean Nuclear Energy Commission (CCHEN).

Benchmark results using OpenMC and MCNP are included in the README file.

**Embargo Notice**:  

This dataset is currently under embargo and will be made publicly available upon acceptance of the associated article. In the meantime, it can be accessed upon reasonable request. Please contact the corresponding author:

- Jaime Romero-Barrientos  - Email: [e-mail]