DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Language and design evolution of the OpenMC Monte Carlo particle transport code

Journal Article · · EPJ Nuclear Sciences and Technologies

The OpenMC Monte Carlo particle transport code has been continuously developed for 13 years by a large community of contributors. In that time span, the codebase has undergone significant changes that have redefined what OpenMC is and made it an enduring presence in the nuclear science and engineering community. In this paper, we discuss the evolution of programming language use in OpenMC, trends in the overall design of the programming interfaces, and implications for the future of the code.

Sponsoring Organization:
USDOE
Grant/Contract Number:
SC0022033
OSTI ID:
2476259
Journal Information:
EPJ Nuclear Sciences and Technologies, Journal Name: EPJ Nuclear Sciences and Technologies Vol. 10; ISSN 2491-9292
Publisher:
EDP SciencesCopyright Statement
Country of Publication:
France
Language:
English

References (8)

OpenMC: A state-of-the-art Monte Carlo code for research and development journal August 2015
Depletion capabilities in the OpenMC Monte Carlo particle transport code journal March 2021
The Random Ray Method for neutral particle transport journal August 2017
FISPACT-II: An Advanced Simulation System for Activation, Transmutation and Material Modelling journal January 2017
Performance Portable Monte Carlo Particle Transport on Intel, NVIDIA, and AMD GPUs journal January 2024
Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code journal March 2019
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE journal May 2011
Recent Developments in the OpenMC Monte Carlo Particle Transport Code conference January 2022

Similar Records

Related Subjects