A Neutron Transport Solver (ANTS)

A Neutron Transport Solution (ANTS) calculates the neutron flux for both criticality and fixed source problems of one dimensional slabs and spheres and two dimensional slabs using the discrete ordinates method. It looks to combine machine learning with collision based hybrid methods and speedup using Cython.

• 1. Running ANTS
  • 1.1. Getting Started
  • 1.2. Standard Inputs
  • 1.3. Homogenized Zones with Multiple Materials
  • 1.4. Preset Two-Dimensional Layouts
  • 1.5. Time-Dependent Problems
  • 1.6. DataTypes Reference
  • 1.7. Examples
• 2. Neutron Transport Equation
  • 2.1. The Continuous Neutron Transport Equation
  • 2.2. The Multigroup Discrete Ordinates Method
  • 2.3. One- and Two-Dimensional Spatial Discretization
  • 2.4. Temporal Discretization Schemes
  • 2.5. Multigroup Neutron Data
• 3. Collision-Based Hybrid Method
  • 3.1. The Collision-Based Hybrid Method
  • 3.2. One Dimensional Collision-Based Hybrid Method
• 4. Method of Nearby Problems
  • 4.1. The Method of Nearby Problems for Fixed Source Problems
  • 4.2. The Method of Nearby Problems for k-Eigenvalue Problems
  • 4.3. Hermite Spline Curve Fit Interpolation
  • 4.4. Curve Fit Residual Formulation
• 5. References