NDPP [Nuclear Data PreProcessor] is a continuous-energy neutron data preprocessing code which converts continuous-energy ACE data to information that is more readily tallied by a Monte Carlo solver for the generation of multi-group cross-sections. Specifically, it integrates the outgoing energy and angular distributions of a reaction to produce a format (Legendre moments or tabular data) and energy group structure defined by the user. NDPP utilizes code written for the OpenMC Monte Carlo neutron transport code.
NDPP is developed by the Adam Nelson and contributors. For more information, feel free to contact the lead developer, Adam Nelson.
The development of OpenMC is led by the Computational Reactor Physics Group at the Massachusetts Institute of Technology.
