Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Performance and accuracy of criticality calculations performed using WARP – A framework for continuous energy Monte Carlo neutron transport in general 3D geometries on GPUs

Journal Article · · Annals of Nuclear Energy
 [1];  [2];  [2];  [2];  [2]
  1. Univ. of California, Berkeley, CA (United States). Dept. of Nuclear Engineering; University of California, Berkeley
  2. Univ. of California, Berkeley, CA (United States). Dept. of Nuclear Engineering

In this companion paper to "Algorithmic Choices in WARP - A Framework for Continuous Energy Monte Carlo Neutron Transport in General 3D Geometries on GPUs" (doi:10.1016/j.anucene.2014.10.039), the WARP Monte Carlo neutron transport framework for graphics processing units (GPUs) is benchmarked against production-level central processing unit (CPU) Monte Carlo neutron transport codes for both performance and accuracy. We compare neutron flux spectra, multiplication factors, runtimes, speedup factors, and costs of various GPU and CPU platforms running either WARP, Serpent 2.1.24, or MCNP 6.1. WARP compares well with the results of the production-level codes, and it is shown that on the newest hardware considered, GPU platforms running WARP are between 0.8 to 7.6 times as fast as CPU platforms running production codes. Also, the GPU platforms running WARP were between 15% and 50% as expensive to purchase and between 80% to 90% as expensive to operate as equivalent CPU platforms performing at an equal simulation rate.

Research Organization:
Univ. of California, Berkeley, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
NA0000979
OSTI ID:
1344092
Alternate ID(s):
OSTI ID: 1429509
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: C Vol. 103; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (12)

Monte Carlo methods for radiation transport analysis on vector computers journal January 1984
Vectorization and parallelization of a production reactor assembly code journal January 1991
Automated scientific software scripting with SWIG journal July 2003
Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code journal May 2010
Algorithmic choices in WARP – A framework for continuous energy Monte Carlo neutron transport in general 3D geometries on GPUs journal March 2015
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data journal December 2011
The NumPy Array: A Structure for Efficient Numerical Computation journal March 2011
Exploiting the Performance of 32 bit Floating Point Arithmetic in Obtaining 64 bit Accuracy (Revisiting Iterative Refinement for Linear Systems) conference November 2006
Using Mixed Precision for Sparse Matrix Computations to Enhance the Performance while Achieving 64-bit Accuracy journal July 2008
On-the-fly elimination of dynamic irregularities for GPU computing journal March 2011
Exploring the tradeoffs between programmability and efficiency in data-parallel accelerators journal June 2011
Stationarity Modeling and Informatics-Based Diagnostics in Monte Carlo Criticality Calculations journal January 2005

Cited By (1)

A Monte Carlo volumetric-ray-casting estimator for global fluence tallies on GPUs journal November 2018

Similar Records

WARP
Software · Wed Apr 12 00:00:00 EDT 2017 · OSTI ID:1357227

WARP
Software · Mon Apr 10 20:00:00 EDT 2017 · OSTI ID:code-5177

The state of Monte Carlo neutron transport on GPU accelerators - A review - 25609
Conference · Wed Aug 15 00:00:00 EDT 2018 · OSTI ID:23055127