Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations

Author(s)
Lund, Amanda L.; Siegel, Andrew M.; Forget, Benoit Robert Yves; Josey, Colin; Romano, Paul Kollath
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Abstract
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 referred to as the cascade grid, is tested within the OpenMC Monte Carlo code, and performance results comparing the method with existing approaches are presented for the Hoogenboom-Martin reactor benchmark. The cascade grid achieves significant speedups in calculation rate with negligible initialization overhead while not increasing the memory footprint by more than 2x. .
Date issued
2015-04
URI
http://hdl.handle.net/1721.1/108585
Department
Lincoln Laboratory; Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Journal
Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. ANS MC2015
Publisher
American Nuclear Society
Citation
Lund, Amanda L., Andrew R. Siege, Benoit Forget, Colin Josey and Paul K. Romano. "Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations" Article presented at the Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. ANS MC2015 (Nashville, Tennessee, April 19–23, 2015).
Version: Author's final manuscript
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