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He Jishu/Nuclear Techniques, ISSN 0253-3219, 10/2017, Volume 40, Issue 10
Journal Article
Nuclear Technology, ISSN 0029-5450, 07/2019, Volume 205, Issue 7, pp. 912 - 927
This paper extends the applicability of the generalized perturbation theory (GPT)-free methodology, earlier developed for deterministic models, to Monte Carlo... 
Monte Carlo, OpenMC | Sensitivity analysis | general perturbation theory-free | general perturbation theory–free | Monte Carlo | NUCLEAR SCIENCE & TECHNOLOGY | OpenMC | GENERALIZED PERTURBATION-THEORY | ALGORITHMS
Journal Article
Nuclear Engineering and Technology, ISSN 1738-5733, 08/2019
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 01/2020, Volume 118, p. 103115
Adopting liquid fuel and on-line reprocessing scenario are the unique features of molten salt reactor (MSR). Considering lattice code for thermal reactor is... 
OpenMC | Molten salt reactor | Fuel cycle simulation | Burnup | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 08/2015, Volume 82, Issue C, pp. 90 - 97
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology.... 
OpenMC | HDF5 | Parallel | Monte Carlo | XML | Neutron transport | NUCLEAR SCIENCE & TECHNOLOGY | PERFORMANCE | TRANSPORT CODE | SIMULATIONS | ALGORITHMS | Industrial research | Algorithms | Nuclear reactors | Analysis | Nuclear facilities | Monte Carlo methods | Computer simulation | Eigenvalues | Extensible Markup Language | Nuclear reactor components | Source code
Journal Article
Nuclear Technology, ISSN 0029-5450, 07/2019, Volume 205, Issue 7, pp. 928 - 944
High-fidelity deterministic transport codes require highly accurate multigroup cross sections (MGXS). Monte Carlo is increasingly cited as a reactor-agnostic... 
OpenMC | Monte Carlo neutron transport | multigroup cross-section generation | NUCLEAR SCIENCE & TECHNOLOGY | NUCLEAR PHYSICS AND RADIATION PHYSICS
Journal Article
He Jishu/Nuclear Techniques, ISSN 0253-3219, 04/2017, Volume 40, Issue 4
Journal Article
Computer Physics Communications, ISSN 0010-4655, 04/2014, Volume 185, Issue 4, pp. 1195 - 1199
We present an energy banding algorithm for Monte Carlo (MC) neutral particle transport simulations which depend on large cross section lookup tables. In MC... 
Monte Carlo | OpenMC | Energy banding | COMPUTER SCIENCE, INTERDISCIPLINARY APPLICATIONS | MODEL | PARTICLE-TRANSPORT | PHYSICS, MATHEMATICAL | RADIATION | Analysis | Algorithms | MATHEMATICS AND COMPUTING
Journal Article
Journal of King Saud University - Science, ISSN 1018-3647, 10/2019, Volume 31, Issue 4, pp. 1271 - 1275
The aim of this study is to validate the reactor physics lattice transport code DRAGON5 and the Monte Carlo code OpenMC by neutronic analysis of critical... 
BAPL | Integral parameters | Code validation | Critical experiments | DRAGON5 | OpenMC | ENDF/B-VII.1 | TRX | MULTIDISCIPLINARY SCIENCES
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 06/2019, Volume 128, pp. 231 - 235
Knowledge of adjoint-weighted kinetics parameters plays an importance role in analyzing the reactor safety and in describing the transient behavior of nuclear... 
Effective neutron generation time | OpenMC | Effective delayed neutron fraction | IFP | CLUTCH | DELAYED NEUTRON FRACTION | MONTE-CARLO CALCULATION | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear energy | Nuclear reactors | Analysis | Nuclear facilities
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 11/2017, Volume 109, pp. 260 - 276
An OpenMC/TANSY code system has been developed in this paper for the coupled neutronics and thermal-hydraulics simulations of MSRs. The homogenized cross... 
OpenFOAM | OpenMC | Finite volume method | MSRs | Coupled neutronics and thermal-hydraulics analysis | FRACTION | NUCLEAR SCIENCE & TECHNOLOGY | BEHAVIOR | MSFR | STEADY-STATE | MODEL | DYNAMICS CODE | Analysis | Nuclear reactors
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 12/2017, Volume 324, pp. 360 - 371
Accelerator driven subcritical system (ADS) is a kind of clean nuclear facility with inherent safety features. ADS facilities mainly put emphasis on studying... 
TTA | Bateman equations | ADS | OpenMC | LLFP | Burnup | Sub-step predictor analysis | REACTORS | NUCLEAR SCIENCE & TECHNOLOGY | EQUATIONS | Analysis | Differential equations | Nuclear facilities
Journal Article
Energy Procedia, ISSN 1876-6102, 09/2017, Volume 127, pp. 264 - 274
PWR core phenomena can be simulated and predicted more precisely and in more details with high-fidelity neutronics and thermal-hydraulics coupling calculation.... 
PSBT benchmark | OpenMC | SUBSC | Coupling | Subchannel
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 12/2017, Volume 110, Issue C, pp. 362 - 383
The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance... 
OpenMC | IFP | Sensitivity analysis | Monte Carlo | Nuclear data | CLUTCH | PERTURBATION | CARLO CODE RMC | MONTE-CARLO | WIELANDT METHOD | NUCLEAR SCIENCE & TECHNOLOGY | NUCLEAR-DATA | COEFFICIENTS | Nuclear energy | Analysis | Nuclear reactors
Journal Article
Nuclear Science and Engineering, ISSN 0029-5639, 01/2017, Volume 185, Issue 1, pp. 184 - 193
In recent years, the use of Monte Carlo methods for modeling reactors has become feasible due to the increasing availability of massively parallel computer... 
Multiphysics | Multiphysics Object-Oriented Simulation Environment | OpenMC | Multiphysics Object-Oriented simulation environment | DISTRIBUTIONS | NUCLEAR SCIENCE & TECHNOLOGY | Monte Carlo method | Usage | Models | Mathematical models | Doppler effect | Monte Carlo methods | Computer simulation | Feedback | Object oriented | Coupling | Moose | Doppler
Journal Article
Nuclear Science and Techniques, ISSN 1001-8042, 1/2019, Volume 30, Issue 1, pp. 1 - 8
The study of accelerator-driven subcritical reactor systems (ADSs) has been an important research topic in the field of nuclear energy for years. The main code... 
Accelerator-driven subcritical system | Energy | Nuclear Physics, Heavy Ions, Hadrons | JENDL4.0/HE | Nuclear Energy | OpenMC | FLUKA | MCNPX | NJOY2016 | CODE | DESIGN | NUCLEAR SCIENCE & TECHNOLOGY | PHYSICS, NUCLEAR | JENDL4
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 04/2018, Volume 114, pp. 329 - 341
Accelerator driven system (ADS) is an advanced nuclear system with high inherent safety feature, which can transmute the nuclear waste including minor... 
ADS | FreeCAD | OpenMC | FLUKA | Ray-casting technology | DESIGN | REACTOR | MYRRHA | BENCHMARKING | NUCLEAR SCIENCE & TECHNOLOGY | Radioactive wastes | Analysis | Computer-aided design
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 02/2018, Volume 112, Issue C, pp. 30 - 41
The multipole representation provides an analytical way of Doppler broadening cross sections for neutron interactions and relies on a partial fraction... 
OpenMC | Doppler broadening | Vector Fitting | Monte Carlo | Multipole | TABULATED CROSS-SECTIONS | NUCLEAR SCIENCE & TECHNOLOGY | REPRESENTATION | DOPPLER | Signal processing | Usage | Hydrogen | Analysis | Methods
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 05/2015, Volume 81, pp. 43 - 52
In this work, OpenMC code has been used for reactor physics calculations of the IAEA 10 MW MTR benchmark. To perform the burnup dependent studies i.e.... 
Monte Carlo methods | MTR benchmark | OpenMC code | Depletion studies | Carlo methods | Monte | NUCLEAR SCIENCE & TECHNOLOGY | Multiplication | Methodology | Mathematical analysis | Nuclear reactor components | Benchmarking | Fluxes | Density
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2018, Volume 111, pp. 224 - 233
This paper serves two purposes. First it demonstrates the validation of newly developed and verified burnup code, inkage of RIGEN and enMC (LOOP) against... 
OpenMC | ORIGEN2.2 | Burnup | LOOP | CODE | NUCLEAR SCIENCE & TECHNOLOGY | HIGH BURNUP | FUEL | CS-134 | Monte Carlo method | Analysis | Nuclear energy | Nuclear power plants | Nuclear reactors
Journal Article
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