Question on energy range of neutron transport by OpenMC

User Support
1

Hi, everyone

I am using OpenMC for my research on ADS, and I have found that OpenMC can transport particles up to the energy in the nuclear data library, that is about 20 MeV.

I have a question: Can OpenMC transport neutron of ~GeV if I use the data library that goes up to higher energy, such as ~GeV energies?

Please forgive me if I have posed the stupid question, and thanks for your time and effort.

2

Hi @VictorL and welcome to the community! Yes, in principle, if you have a data library that goes up to GeV, OpenMC would allow you to transport neutrons up to whatever the maximum is. I would caution you however that it would likely not correctly handle the resulting shower of secondary particles. At those energies, you are most likely better off with a code intended for high-energy physics such as Geant4.

3

OK! Thank you very much!