Nuclear Engineering and TechnologyIn order to support the verification of neutronics/thermal-hydraulics coupling calculation method or simulation codes at the fine mesh for plate-type pressurized water reactor (PWR) with high parameters (which the ratio of power to mass flow rate is ...
Zhigang Li +10 more
doaj +1 more source
EnergiesThe High-Temperature Gas-Cooled Pebble Bed Reactor (HTG-PBR) is notable in the advanced reactor realm for its online refueling capabilities and inherent safety features.
Kashminder S. Mehta +2 more
doaj +1 more source
Calculations of kinetic parameters of LFR with the OpenMC Monte Carlo code [PDF]
This work investigates the different methods used to analyze the effective delayed neutron fraction, βeff, and the effective mean generation time, Λeff, in the OpenMC code, with a particular focus on Lead-cooled Fast Reactors.
Olivares, Darian Andrés
core
Neutronic Analysis of Larger Fuel Pins in the Experimental Breeder Reactor-II [PDF]
Det globale energibehovet forventes å øke betydelig i løpet av de kommende tiårene, samtidig som behovet for raske reduksjoner i CO2-utslipp øker. I denne sammenhengen fremstår kjernekraft som et lovende lavutslippsalternativ som kan levere pålitelig ...
Jensen, Jostein Bjørvik +2 more
core
Neutron transport analysis of a supercritical water small modular reactor [PDF]
A detailed model of the ECC-SMART small-modular supercritical-water reactor has been made using the OpenMC Monte Carlo code by developing three models with different levels of fidelity: a 2D infinite lattice pin-cell model, a 3D finite-length fuel ...
Villafañe, Juan Ignacio
core
Demand driven salt clean-up in a molten salt fast reactor - Defining a priority list. [PDF]
PLoS One, 2018 Merk B, Litskevich D, Gregg R, Mount AR.
europepmc +1 more source
Evaluating machine learned nuclear data precision in full core nuclear reactor Monte Carlo neutronics and computational efficiency analyses. [PDF]
Sci RepHashemi A, Macián-Juan R, Ohlerich M.
europepmc +1 more source
Sensitivity-informed framework for enrichment distribution in MNR for thermal performance enhancement. [PDF]
Sci RepAziz U +5 more
europepmc +1 more source
Partial Cross-Section Calculations for PGNAA Based on a Deterministic Neutron Transport Solver [PDF]
, 2022 Frank, Martin +2 more
core +2 more sources
Development of a novel machine learning-based adaptive resampling algorithm for nuclear data processing. [PDF]
Sci RepHashemi A, Macián-Juan R, Ohlerich M.
europepmc +1 more source