ATR NSUF Experiment Design Toolkit¶

We assume that the reader seeks to conduct a quick, efficient, and reasonably accurate computational neutronic analysis on an irradiation experiment in the ATR-3 core. This guide provides step by step instructions on how to conduct such an analysis using the “substitution” method. The guide covers two different computational options through which “substitution” method can be implemented: the MCNP5 option and the DAG-MCNP5 (DAGMC) option. The MCNP5 option is faster and more computationally efficient, while the DAGMC option is more “user-friendly”, particularly for those who are not proficient in the language of MCNP.