Papers using OpenMC

Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel

1 Like

Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction

Performance of different absorber materials and move-in/out strategies for the control rod in small rod-controlled pressurized water reactor: A study based on KLT-40 model

1 Like

An improved optical length research on the physical boundary of particle-dispersed fuel

Shameless plug for a recently published paper by @eepeterson @pshriwise and myself :smile:
Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC

2 Likes

Modeling gamma detectors in OpenMC: Validation of a newly implemented pulse-height tally

4 Likes

More fusion-related work from the good folks at MIT:
OpenMC Interpretation of FNS SINBAD Shielding Benchmark Experiments

1 Like

Tetris-inspired detector with neural network for radiation mapping

Exploring Effects of Homogenization on an OpenMC Depletion Analysis of a TRISO Fueled, Helium Cooled Microreactor

2 Likes

Advancements in Multiphysics Microdepletion Analysis of an eVinci™-like Microreactor Leveraging OpenMC-CRAB Workflow

1 Like

HighNESS conceptual design report: Volume I

1 Like

Comparative Irradiated Dimensional Change Strain Analyses of Two Types of Graphite Components in a Thorium Molten Salt Reactor

Neutronic Analysis of Accident-Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes

Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix
Approach Coupled to OpenFOAM

1 Like

OFELIA: An OpenMC-FEniCSx coupling for neutronic calculation with temperature feedback

1 Like

Analysis of the LatticeNet neural network framework’s performance using prediction-calculated temperature coefficients in PWR assemblies

Simulation of in-core neutron monitoring with U-235 micro fission chamber for CiADS-like LFR

Multi-physical coupling study of neutronics/thermal-hydraulics/material corrosion based on the unified coupling framework

1 Like

Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor

MANTA: a negative-triangularity NASEM-compliant fusion pilot plant

Burnup study on the effective transmutation of minor actinides based on multi-enrichment fuel in the ADS subcritical reactor

Neutronics simulations for the design of neutron flux monitors in SPARC

Digital: accelerating the pathway

Control strategy for the core power in an accelerator drive sub-critical system