Implementation and Validation of Photon Transport in OpenMC
Abstract
OpenMC is a Monte Carlo particle transport code focused on reactor physics calculations. It stochastically simulates neutrons moving through 3D models using constructive solid geometry and continuousenergy cross sections. Recently, a photon transport capability was added to OpenMC. In reactor simulations, photon transport is needed, for example, to account for photon heating: although the majority of the energy deposited at a fission site comes from the kinetic energy of the fission fragments, a nontrivial portion can be carried away by photons. Therefore, photons produced in neutron reactions must be simulated in order to accurately model energy deposition. OpenMC can now simulate neutroninduced photon production as well as perform pure photon calculations. The four basic photon interactions with matter — coherent (Rayleigh) scattering, incoherent (Compton) scattering, the photoelectric effect, and pair production — are modeled. Secondary processes that can create new photons (i.e., atomic relaxation, electronpositron annihilation, and bremsstrahlung) are also included. The methods implemented here were validated against MCNP6 for a variety of materials and energies.
 Authors:

 Argonne National Lab. (ANL), Argonne, IL (United States)
 Publication Date:
 Research Org.:
 Argonne National Lab. (ANL), Argonne, IL (United States)
 Sponsoring Org.:
 USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR)
 OSTI Identifier:
 1490825
 Report Number(s):
 ANL/MCSTM381
149145
 DOE Contract Number:
 AC0206CH11357
 Resource Type:
 Technical Report
 Country of Publication:
 United States
 Language:
 English
Citation Formats
Lund, Amanda L., and Romano, Paul K. Implementation and Validation of Photon Transport in OpenMC. United States: N. p., 2018.
Web. doi:10.2172/1490825.
Lund, Amanda L., & Romano, Paul K. Implementation and Validation of Photon Transport in OpenMC. United States. https://doi.org/10.2172/1490825
Lund, Amanda L., and Romano, Paul K. 2018.
"Implementation and Validation of Photon Transport in OpenMC". United States. https://doi.org/10.2172/1490825. https://www.osti.gov/servlets/purl/1490825.
@article{osti_1490825,
title = {Implementation and Validation of Photon Transport in OpenMC},
author = {Lund, Amanda L. and Romano, Paul K.},
abstractNote = {OpenMC is a Monte Carlo particle transport code focused on reactor physics calculations. It stochastically simulates neutrons moving through 3D models using constructive solid geometry and continuousenergy cross sections. Recently, a photon transport capability was added to OpenMC. In reactor simulations, photon transport is needed, for example, to account for photon heating: although the majority of the energy deposited at a fission site comes from the kinetic energy of the fission fragments, a nontrivial portion can be carried away by photons. Therefore, photons produced in neutron reactions must be simulated in order to accurately model energy deposition. OpenMC can now simulate neutroninduced photon production as well as perform pure photon calculations. The four basic photon interactions with matter — coherent (Rayleigh) scattering, incoherent (Compton) scattering, the photoelectric effect, and pair production — are modeled. Secondary processes that can create new photons (i.e., atomic relaxation, electronpositron annihilation, and bremsstrahlung) are also included. The methods implemented here were validated against MCNP6 for a variety of materials and energies.},
doi = {10.2172/1490825},
url = {https://www.osti.gov/biblio/1490825},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {12}
}