MontePy

MontePy is a Python interface designed to efficiently handle MCNP® input files. It provides functionalities to read, edit, create, and write MCNP® input files. MCNP® is a code developed by Los Alamos National Laboratory for simulating radiation transport problems using Monte Carlo methods.

MontePy is specifically tailored for MCNP® users with intermediate Python programming skills. It enables automated modifications to large simulations and aims to simplify the process of making large-scale modifications to MCNP® problems. This is particularly beneficial for neutronics analysts working with research reactors and simulating fusion reactors. MontePy can also be utilized by software developers who maintain specialty software for working with MCNP® input files. It offers several advantages, such as being open-source, having a modular design, and providing a detailed developer's guide. Compared to directly working with MCNP® input files, MontePy provides a more intuitive user experience. Its goal is to reduce the time required for generating and updating MCNP® models, eliminate tedious tasks, and enhance productivity. Furthermore, it minimizes the risk of human error and enables new possibilities, such as automating sensitivity studies.

This software is open source and available at no cost. Download now by visiting the product's GitHub page.