Papers using OpenMC

Announcements
205

Power distribution reconstruction from in-core detector measurements using gaussian process regression

206

Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector

1 Like
207

I don’t usually post preprints but this one has created some buzz:
Scalable Chrysopoeia via (n,2n) Reactions Driven by Deuterium-Tritium Fusion Neutrons

208

Neat paper by @nuclearbae:
Neutronics analysis of spin-polarized fuel in spherical tokamaks

209

Development of a steady-state single-channel model of the BAEC 3MWt TRIGA mark-II research reactor for thermal and hydrodynamic analysis

And a new paper by yours truly:
Computing material volume fractions on a superimposed mesh as applied to Monte Carlo particle transport simulations

210

Physics-Informed Plasma Profile Input for OpenMC Fusion Neutronics

211

Neutronics and Activation Analysis of Aluminized RAFM Steel

Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo

Three-dimensional refined burnup characteristics analysis of Helical Cruciform Fuel

212

Consistent Method for Calculating Directional Diffusion Coefficients Using Monte Carlo

213

Extending Embedded Monte Carlo as a novel method for nuclear data uncertainty quantification

214

Evaluation of an Autonomous Robotic System for Reducing Radiation Risk in a Real-World Cardiac Imaging Laboratory

215

Extension of the OpenMC depletion module for transport-independent depletion

216

Activation analysis of a compact Tokamak using Deuterium–Helium3 fuel

217

Simulating hydrogen diffusion in a zirconium hydride moderator block and its impact on steady state neutronic-thermal behavior

218

New article out from @fnovais and @eepeterson:
FNG HCPB Tritium Breeder Module Mock-Up Benchmarking of OpenMC and Uncertainty Quantification

219

Simulation of NuScale-Like SMR Benchmark with OpenMC Code