Review of the natC(n,γ) cross section and criticality calculations of the graphite moderated reactor BR1.

Highlights: [•] Review of the experimental and evaluated data for natC(n,γ) and 12C(n,γ). [•] Comparison of ENDF/B-VII.1 and JEFF-3.1.2 within BR1 criticality calculations. [•] The thermal capture cross section is of importance in large graphite-systems like BR1. [•] The 12C(n th ,γ) given by Firestone and Révay (2011) is recommended to be used. [•] The JENDL-4.0 evaluation takes the latest experimental data available. [ABSTRACT FROM AUTHOR]