Results 151 to 156 of about 538 (156)

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

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

Performance evaluation and validation of OpenMC code for criticality analysis of an MTR-type research reactor

Annals of Nuclear Energy
exaly