BTRR model development and verification for Monte Carlo simulation

The Bangladesh Atomic Energy Commission's TRIGA Mark II research reactor (BTRR), located near Dhaka, has been operational since September 1986, primarily for training, education, radioisotope production, and research. Currently, the Reactor Physics and Engineering Division is enhancing its analysis methods by employing modern tools like high-fidelity Monte Carlo analysis and introducing advanced codes and cross-section libraries. This study details the new reactor model implemented by means of the OpenMC code using the nuclear cross-section data libraries based on the ENDF/B-VIII.0 and ENDF/B-VII.1, focusing on calculating critical reactor parameters such as core excess reactivity, shutdown margin, control rod worth, power peaking factors, etc. The accuracy of the model verified by comparisons with previous calculations and experimental data showed good agreement.