Papers using OpenMC

Announcements
225

Impact of high-fidelity temperature feedback modeling on fusion blanket neutronics

2 Likes
226

New paper by @paulromano @pshriwise @eepeterson

Implementation of the D1S Methodology for Shutdown Dose Rate Calculations in the OpenMC Monte Carlo Particle Transport Code

1 Like
227

Preliminary Verification of Fixed-Source Sensitivity Analysis in OpenMC

228

Evaluation of simulated HPGe detector efficiencies in OpenMC compared to MCNP

229

Thermomechanics coupling to Monte Carlo particle transport on unstructured mesh geometries using Cardinal

230

Deuterium-Tritium Levitated Dipole Fusion Power Plants

231

Depletion Perturbation Theory Methodology for Analyzing the Sensitivity of Advanced Activation Chains

Calculation of Adjoint-Weighted Kinetics Parameters in OpenMC Using the Iterated Fission Probability Method

1 Like
232

New thorium core loading patterns for high temperature gas cooled nuclear microreactors

A novel discontinuous-Galerkin deterministic neutronics model for fusion applications: workflow for stellarator reactor design studies

Machine Learning-Based Inversion of Axial-Segment Characterization for Spent Fuel Materials

233

A Novel Multi-Point Depletion Model for Molten Salt Reactors

Core Design and Fuel Cycle Analysis of the Wielenga Innovation Salt Tank Reactor (WISTR) with Online Refueling

234

Neutronic Analysis of a Single Fuel Pin Cell from the APR1400 Benchmark Using the DRAGON5 and OpenMC Codes

235

An open source multiphysics workflow for the analysis of subcritical transmutation systems

236

Enhancing fast neutron irradiation in thermal neutron spectrum reactors through python-based multi-objective optimization

237

OpenMC-Fusion-Benchmarks, a CAD-Based Automated Framework for Fusion Neutronics Validation

238

Collision Tracking in OpenMC: Methods and Applications in Neutron Noise, Neutron Imaging, Time-of-Flight, and Multiplicity Counting