The OpenMC Monte Carlo particle transport code
Name
annals-openmc.pdf
Description
Main article
Size
226.82 KB
Format
Adobe PDF
Checksum (MD5)
3fbe4319d24a7653c2f5d91b4a0569c0
Author(s)
Romano, Paul Kollath
Forget, Benoit Robert Yves
Date Issued
October 2012
Journal
Annals of Nuclear Energy
Publisher
Elsevier
Citation
Romano, Paul K. and Forget, Benoit. “The OpenMC Monte Carlo Particle Transport Code.” Annals of Nuclear Energy 51 (January 2013): 274–281. © 2012 Elsevier Ltd
Version
Author's final manuscript
Abstract
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute of Technology as a tool for simulation on high-performance computing platforms. Given that many legacy codes do not scale well on existing and future parallel computer architectures, OpenMC has been developed from scratch with a focus on high performance scalable algorithms as well as modern software design practices. The present work describes the methods used in the OpenMC code and demonstrates the performance and accuracy of the code on a variety of problems.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-NonCommercial-NoDerivs License
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1016/j.anucene.2012.06.040
