An NCrystal extension for thermal neutron scattering in MCNP

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Abstract

A new extension for MCNP has been developed that incorporates the NCrystal thermal scattering package in the form of a Fortran to C++ wrapper, which adds the capability to describe thermal neutron scattering in the NCrystal formalism instead of the ACE tabular format. This can be used to described poly- or single-crystalline materials as well as liquids. The functionality of this extension to MCNP is illustrated using a layered crystal monochromator, leakage of neutrons from a moderating sphere of material, and by simulating criticality benchmarks.

Keywords

  • MCNP
  • Monte Carlo neutron transport
  • Particle tracking
  • Radiation shielding

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