Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations
We describe and test a technique for carrying out energy grid searches in continuous-energy Monte Carlo (MC) neutron transport calculations that represents an optimal compromise between grid search performance and memory footprint. The method, based on the fractional cascading technique and referre...
Main Authors: | Lund, Amanda L., Siegel, Andrew M., Forget, Benoit Robert Yves, Josey, Colin, Romano, Paul Kollath |
---|---|
Other Authors: | Lincoln Laboratory |
Format: | Article |
Language: | en_US |
Published: |
American Nuclear Society
2017
|
Online Access: | http://hdl.handle.net/1721.1/108585 https://orcid.org/0000-0003-1459-7672 https://orcid.org/0000-0002-3210-5806 https://orcid.org/0000-0002-1147-045X |
Similar Items
-
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations
by: Romano, Paul Kollath, et al.
Published: (2012) -
Multi-core performance studies of a Monte Carlo neutron transport code
by: Siegel, A. R., et al.
Published: (2017) -
The OpenMC Monte Carlo particle transport code
by: Romano, Paul Kollath, 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)