Hello, I am using OpenMC 0.14.0 on HiPerGator at UF (HPC) to simulate a basic fusion reactor comprising of plasma, firstwall, and blanket. I am using paramak to generate this geometry, then converting to h5m. I was adjusting parameters in paramak until my geometry would function in OpenMC without losing any particles, and I was able to achieve that but now I have a new error. I have encountered it previously when attempting a trial run on a reactor also from paramak. I am attempting to create a fixed neutron source and run deplete to then generate gamma sources in the geometry similar to what I have found in the fusion neutronics workshop GitHub. The issue is that one or two initial neutron batches will run, but then OpenMC returns a Segmentation Fault Error and the simulation ends. I can send both the script and output as needed.