Results 161 to 170 of about 898 (171)

Implementation of Triply Periodic Minimal Surfaces in Openmc

Paul Alexandre Ferney, Nicolas Pierre Martin   +1 more
openaire   +1 more source

Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code

Nuclear Technology, 2019
William Boyd, Adam G Nelson, Paul K Romano   +2 more
exaly  

Development and Benchmarking of a Relativistic Point Detector in Openmc

Itay Horin, Or Alon, Arik Kreisel, Tsviki Hirsh, Tamar Dayan, Hallel Fuks   +5 more
openaire   +1 more source

Neutronic Investigation of Uranium Silicide using OpenMC

Sumaiya Islam, Zubair, Lamia, Mosharat Belal Tahia, Abdus Sattar Mollah   +3 more
openaire   +1 more source

Activation Calculation Comparison for FISPACT-II, ORIGEN, and OpenMC

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
Jin Bae, Yves Robert
openaire   +1 more source

An OpenMC model of the SPARC tokamak for the diagnostic scoping studies

Fusion Engineering and Design
X. Wang, R. Gocht, J. Ball, S. Mackie, E. Panontin, E. Peterson, P. Raj, I. Holmes, A.A. Saltos, A. Johnson, A. Grieve, R.A. Tinguely   +11 more
openaire   +1 more source

Transient Monte Carlo simulations with OpenMC(TD): A catalyst towards advancing research in next-generation reactors and to improve fission nuclear data

Nuclear Engineering and Design
J Romero-Barrientos, F Molina
exaly  

Validation of OpenMC Using the KRUSTY Component Critical Experiments

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
Michael Mendes, April Novak
openaire   +1 more source

Validation of SNAP-10A reactor core criticality experiment benchmark based on OpenMC

Radiation Physics and Chemistry
Zelong Zhao
exaly  

Evaluation of Applicability of Geant4 and OpenMC in Tritium Breeding Calculation for Fusion Blanket

Journal of Fusion Energy
Shiteng Zhang, H.B. Guo, J.M. Ma, Jingyu Sun   +3 more
openaire   +1 more source