Monte Carlo domain decomposition for robust nuclear reactor analysis
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simulations, but they cannot be robustly applied to high-fidelity nuclear reactor analysis without accommodating several terabytes of materials and tally data. While this is not a large amount of aggregate...
Main Authors: | Siegel, Andrew, Horelik, Nicholas Edward, Forget, Benoit Robert Yves, Smith, Kord S. |
---|---|
Other Authors: | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering |
Format: | Article |
Language: | en_US |
Published: |
Elsevier
2017
|
Online Access: | http://hdl.handle.net/1721.1/107915 https://orcid.org/0000-0003-1459-7672 https://orcid.org/0000-0003-2497-4312 |
Similar Items
-
Domain decomposition for Monte Carlo particle transport simulations of nuclear reactors
by: Horelik, Nicholas E. (Nicholas Edward)
Published: (2015) -
Progress and Status of the Openmc Monte Carlo Code
by: Siegel, Andrew R., et al.
Published: (2017) -
On the use of tally servers in Monte Carlo simulations of light-water reactors
by: Siegel, Andrew, et al.
Published: (2017) -
Data decomposition of Monte Carlo particle transport simulations via tally servers
by: Siegel, Andrew R., et al.
Published: (2017) -
OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development
by: Nelson, Adam G., et al.
Published: (2017)