User’s Guide

Welcome to the OpenMOC User’s Guide! This tutorial will guide you through the essential aspects of using OpenMOC to perform neutron transport reactor physics calculations.

• 1. A Beginner’s Guide to OpenMOC
  • 1.1. What does OpenMOC do?
  • 1.2. How does it work?
  • 1.3. What do I need to know?
• 2. Installation and Configuration
  • 2.1. Prerequisites
  • 2.2. Obtaining the Source
  • 2.3. Building From Source
  • 2.4. Installing with Docker
• 3. Writing Python Input Files
  • 3.1. Simulation Parameters
  • 3.2. Simulation Log Files
  • 3.3. Specifying Materials and Geometry with OpenMC’s MGXS module
  • 3.4. OpenMOC Materials Specification
  • 3.5. OpenMOC Geometry Specification
  • 3.6. Track Generation
  • 3.7. MOC Source Iteration
  • 3.8. CMFD Acceleration
  • 3.9. References
• 4. Data Processing and Visualization
  • 4.1. Exporting Simulation Data
  • 4.2. Retrieving Simulation Data
  • 4.3. Computing Reaction Rates
  • 4.4. Geometry Visualization
  • 4.5. Flux Visualization
  • 4.6. Fission Rate Visualization
  • 4.7. Flux eigenmodes Visualization
  • 4.8. Generalized Spatial Visualization
  • 4.9. Angular Quadrature Visualization
• 5. Running OpenMOC
  • 5.1. Running OpenMOC in the Shell
  • 5.2. Submitting a TORQUE Job
  • 5.3. Submitting a SLURM Job
  • 5.4. Submitting a Cobalt Job
  • 5.5. Runtime Options
  • 5.6. Canceling an OpenMOC Simulation
• 6. Troubleshooting
  • 6.1. Problems with Compilation