The NDPP program is a code which extracts nuclear data from ACE format data files (used by the Monte Carlo neutron transport codes MCNP, Serpent, and OpenMC, among others), to a form more readily tallied by the Monte Carlo codes. Specifically, NDPP integrates outgoing particle angle and energy probability distributions from both scattering and fission reactions over outgoing energy and/or angle to produce a quantity which only depends on incoming neutron energy, significantly increasing the convergence rate. The project started under the Fission Systems and Radiation Transport group at the University of Michigan.
Detailed installation instructions can be found in the User's Guide.
If you run into problems compiling, installing, or running NDPP, first check the Troubleshooting section in the User's Guide. If you are not able to find a solution to your problem there, please contact the developer.
NDPP is hosted on BitBucket and all bugs are reported and tracked through the Issues feature on BitBucket. However, BitBucket Issues should not be used for common troubleshooting purposes. If you are having trouble installing the code or getting your model to run properly, you should first send a message to the developer. If it turns out your issue really is a bug in the code, an issue will then be created on BitBucket. If you want to request that a feature be added to the code, you may create an Issue on BitBucket.
NDPP is distributed under the MIT/X license.