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MNP

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Package for handling Multiphysics Neutronics systems. Requires numpy and numba.

Run the software with

$python wrapper.py material.npz input.in

material.npz specifies the material parameter used for the simulation. This .npz file has the following numpy arrays:

  1. E, Energy grid boundaries, [1xG+1]
  2. SigmaT, Total cross section, [1xG]
  3. SigmaF, Fission cross section, [1xG]
  4. SigmaS, Scattering cross section [GxG]
  5. v, Speed in energy group [1xG]
  6. nu_prompt, Neutrons per prompt fission, [1xG]
  7. nu_delayed, Neutrons per delayed fission, [1xG]
  8. chi_prompt, Probability of prompt fission, [GxG]
  9. chi_delayed Probability of delayed fission, [GxJ]
  10. decay, Decay constant for precursor [1xJ]
  11. beta_frac, Probability of prompt fission, [1xJ]

Input.in specifies simulation parameters. It is self documenting.

Two example problems have been included, a subcritical problem and a delayed supercritical problem. These can be run with the previously mentioned command and varying the input file between the two choices. A rudementary plotting script has been included in the Outputs directory to visualize the output on a very basic level.

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Package for handling Multiphysics Neutronics systems

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