User Manual¶
- 1. Running the RMC Code
- 2. Input Overview
- 3. Geometry
- 4. Material
- 4.1. Material Input Options under the ACE Format Database
- 4.2. Material Input Card Based on HDF5 Format AIS Database
- 4.3. Continuous energy ACE cross-section related Input Options
- 4.4. OTFDB Nuclide Input Card
- 4.5. Material HDF5 File Input
- 4.6. Multi-group ACE Cross-Section Related Input Card
- 4.7. Photonuclear reaction and photogenic reaction database selection input option
- 4.8. Input Option for Adjusting the Average Fission Neutron Number
- 4.9. Dynamic material related input options
- 4.10. Input Card for Continuously Varying Material
- 4.11. Material module input example
- 5. Mesh
- 6. Criticality Calculations
- 6.1. Source Iteration Parameters
- 6.2. UFS Mesh Parameters
- 6.3. Initial fission source
- 6.4. External Source Subroutines
- 6.5. Random Number Generator
- 6.6. Truncation Conditions
- 6.7. Parallel Criticality Calculation Mode
- 6.8. Fission Matrix Method for Solving Critical Adjoint Flux
- 6.9. Output counting results generation by generation
- 6.10. Criticality calculation module input example
- 7. Tally
- 8. Energy Release and Deposition
- 9. Source Convergence Diagnosis and Acceleration
- 10. Burnup Calculations
- 11. Depletion Calculations
- 12. Output Control
- 13. Plot
- 14. Fixed Source Calculations
- 14.1. Total number of simulated particles
- 14.2. Adjoint Calculations
- 14.3. Random Number Generator
- 14.4. Truncation Conditions
- 14.5. Dynamic Load Balancing for Fixed-Source Calculations (Enterprise Edition Only)
- 14.6. External Source Subroutines for Fixed-Source Calculations
- 14.7. Fixed source module input example
- 15. Space-time Dynamics Calculations (Enterprise Version Only)
- 16. Material Perturbation (Enterprise Version Only)
- 17. Criticality Search (Enterprise Version Only)
- 18. Calculations for Iterated Fission Probability Method
- 19. Domain Decomposition (Enterprise Version Only)
- 20. Sensitivity and Uncertainty Analysis (Enterprise Version Only)
- 21. Source Description
- 22. Neutron Transport Calculations
- 23. Photon Transport Calculations
- 24. Electron Transport Calculations
- 25. Homogenized Group Constants (Enterprise Version Only)
- 26. Cross-section Parameterization Function (Enterprise Version Only)
- 27. Checkpoint Continuation Calculation
- 28. Continuation Surface Source
- 29. Particle Event Tracking (Enterprise Version Only)
- 30. INCLUDE File Inclusion Feature
- 31. Variance Reduction
- 32. Stochastic Neutron Dynamics (Enterprise Version Only)
- 33. Neutron Coincidence Tally (Enterprise Version Only)
- 34. Serialized Restart Calculation
- 35. CONTROL Option Card
- 36. Neutronics-Thermal Coupling Iterative Calculation (Enterprise Version Only)
- 37. Refuelling
- 38. Appendix