Project made by Catherine Dickstein and Jack Szprowski
For the UMD Radiation Facility
In Order To Simulate The Flux That Occurs In Neutron Imaging
The main_sim.py file can be used to simulate the amount of flux going through an ideal bronze cylinder. We developed the program to gather data for an experiment on the porosity of 3d-printed metals. From the simulated flux, we calculated the expected attenuation of neutrons. This value was then compared to the experimental attenuation measured with a MUTR Neutron Imager.
Link to Google Sheet and all data and calculations
We followed the Neutronics Workshop instructions to run our simulation. There are other ways to do this, which are listed here on the OpenMC documentation. Below is a summarized process:
- Install Docker
- Launch OpenMC in a Jupyter Notebook
- Open main_sim.py
Citation
Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit Forget, and Kord Smith, "OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development," Ann. Nucl. Energy, 82, 90--97 (2015).