1.1. Getting Started#
The ANTS package solves the discrete ordinates neutron transport equation in one-dimensional (slab and sphere), two-dimensional (rectangular), and three-dimensional (rectangular) geometry. Three-dimensional problems are currently limited to fixed source problems.
Problem Types Supported:
Fixed source problems: Given an external source and/or boundary source, compute the steady-state flux
Time-dependent problems: Solve transient problems with temporal evolution
Criticality (k-eigenvalue) problems: Find the effective multiplication factor and fundamental eigenmode
Acceleration Methods:
Hybrid methods: Collision-based decomposition for time-dependent problems
DMD (Dynamic Mode Decomposition): Reduced-order acceleration for multigroup problems
Discretizations:
Spatial: Step characteristic method or diamond difference
Angular: Discrete ordinates (product quadrature sets)
Energy: Multigroup formulation
Time: BDF1 (backward Euler), BDF2, Crank-Nicolson (CN), and TR-BDF2
1.1.1. Installation#
1.1.2. Required Input Data#
To solve a neutron transport problem, you need:
Cross-sectional data for each material: - Total cross section (\(\sigma^{\mathrm{t}}\)) - Scattering matrix (\(\sigma^{\mathrm{s}}\)) - Fission matrix (\(\chi \, \nu \, \sigma^{\mathrm{f}}\))
Geometry specification: spatial cells, material locations, dimensions
Angular quadrature: discrete directions and weights
Source terms: external source and/or boundary conditions
Parameters: problem configuration (geometry type, discretization, time stepping, etc.)
1.1.3. Current Limitations#
No beta decay or delayed neutrons
No temperature feedback or Doppler effects
1.1.4. Notation#
Throughout the documentation, the following notation is used for problem dimensions:
\(I\) : Number of spatial cells in the x direction
\(J\) : Number of spatial cells in the y direction
\(K\) : Number of spatial cells in the z direction (3D)
\(N\) : Number of discrete angles (1D), \(N^2\) total angles (2D), or the total number of ordinates (3D, \(2 N^2\) for
angular_xyz(N))\(G\) : Number of energy groups
\(T\) : Total elapsed time
\(M\) : Number of different materials