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

1 Like
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

1 Like
220

Multi-step verification of the Copenhagen atomics molten salt experiment radioactive inventory at the Paul Scherrer Institute using OpenMC, Serpent, and EQL0D

A comparative study on the neutronic characteristics of the new four-petal and three-petal helix fuel assemblies

Conceptual design and preliminary feasibility study of fluid-driven suspended control rods for molten salt reactors

221

Preliminary design and neutronic characterisation of a 200 kWt HALEU fueled heat-pipe reactor for space applications

Ensuring Subcriticality of Space Lithium-Cooled Reactors During Submerged Accidents: A Study on Ex-Core Reactivity Control

Accelerated solution methods for self-adjoint angular flux neutron transport equations based on scattering matrix decoupling

Assessment of structural materials in compact fusion reactor design

Measurements of fusion yield on the Centrifugal Mirror Fusion Experiment

222

Negative fluxes and cell-miss errors in the random ray method

1 Like
223

Validation of OpenMC for advanced graphite-moderated/reflected reactors: insights from benchmarking the UFTR

2 Likes
224

Spectrum-Dependent Burnable Poison Selection for Enhanced Safety and Neutronic Performance in an Epithermal Supercritical Carbon Dioxide-Cooled Reactor

Investigation of evaluated nuclear data in the prediction of inherent neutron sources

Evaluating machine learned nuclear data precision in full core nuclear reactor Monte Carlo neutronics and computational efficiency analyses

1 Like