Papers using OpenMC

Announcements
83

Heterogeneous model based burnup and its impact on integral parameters of IAEA MTR benchmark

84

Application of functional expansions Tally (FET) filter in a gas-cooled fast reactor design

1 Like
85

Neat work going on at MIT by @eepeterson and friends:
The LIBRA Experiment: Investigating Robust Tritium Accountancy in Molten FLiBe Exposed to a D-T Fusion Neutron Spectrum

and another fusion work:
Preliminary investigation of neutron shielding compounds for ARC-class tokamaks

1 Like
86

Conceptual design and its optimization of an air-cooled nuclear reactor for aircraft propulsion considering both thermal and neutronic performance

87

Nice paper on multiphysics work by @helen-brooks and @makeclean:
Scalable multi-physics for fusion reactors with AURORA

88

Study of the neutronic and thermal coupling effect on VHTR fuel pebble using OpenMC and OpenFOAM

89

In the same issue, I found also the following paper
Impact of the TRISO fuel homogenisation approximation in the MHTGR

90

Convergence characteristics and acceleration of the transient fixed source equation solved by Monte Carlo method

91

Nuclear data uncertainty propagation and implications for radioactive waste management of fusion steels

92

Simulation of a NaI(Tl) detector model using OpenMC modified on code source and validation using experimental and simulated results

93

Hello all,

I would like to share with you a paper we published.

Radiation shielding properties of modified concrete mixes and their suitability in dry storage cask

Regards,
Maria

2 Likes
94

Integrated simulation for the preconceptual optioneering of the STEP breeder blanket design

1 Like
95

Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design

96

Transmutation of MAs and LLFPs with a lead-cooled fast reactor

97

Tetris-inspired detector with neural network for radiation mapping
FSAR: Full neutron spectrum code for advanced reactor simulation
Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC(TD)

1 Like
98

The Influence Mechanism of Space-Time Kinetics of ADS Subcritical Reactor under Beam Transients

1 Like
99

Radiation characteristics analysis for spallation products of lead–bismuth target and tungsten–iron–nickel target
Neutronic Evaluation and Optimization of the Centrifugal Nuclear Thermal Rocket Concept

1 Like
100

Advancing Methods for Fusion Neutronics: An Overview of Workflows and Nuclear Analysis Activities at UKAEA

1 Like
101

Linear Regression and Machine Learning for Nuclear Forensics of Spent Fuel from Six Types of Nuclear Reactors

Improved Methods for Calculating the Neutron Diffusion Coefficient of General Pebble Bed

1 Like
102

Neat paper that showcases the recent NCrystal integration in OpenMC:
Advances in Nuclear Data and Software Development for the HighNESS Project