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Title: OpenMC: A state-of-the-art Monte Carlo code for research and development

Journal Article · · Annals of Nuclear Energy

Sponsoring Organization:
USDOE
OSTI ID:
1249661
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 82 Journal Issue: C; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United Kingdom
Language:
English
Citation Metrics:
Cited by: 272 works
Citation information provided by
Web of Science

References (10)

The OpenMC Monte Carlo particle transport code journal January 2013
The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations journal December 1972
Multi-core performance studies of a Monte Carlo neutron transport code journal January 2013
Direct Doppler broadening in Monte Carlo simulations using the multipole representation journal February 2014
Improved cache performance in Monte Carlo transport calculations using energy banding journal April 2014
The effect of load imbalances on the performance of Monte Carlo algorithms in LWR analysis journal February 2013
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations journal February 2012
Efficiency Improvement of Local Power Estimation in the General Purpose Monte Carlo Code MCNP journal January 2011
Data decomposition of Monte Carlo particle transport simulations via tally servers journal November 2013
Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation journal July 2009

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