affiliation not provided to SSRN
Gas-liquid two-phase flow, Rod bundle subchannel, Void fraction distribution, Bubble geometric restriction
Helical-coiled steam generator, Helical-coiled tube bundles, Liquid metal, Helix angle
Conical type swirl-vane separator, flow filed, separation performance, structure optimization, simulation
Steam jet condensation, Synchronous measurement, pressure oscillation, Direct contact condensation, Multiphase Flow
Coarse-mesh, Thermohydraulic analysis, Empirical correlation, Lumped parameter, Spacer effects
Heat pipe reactor, Burnable poison, Multiphysics analysis, Hydrogen dissociation
helically coil tube, gas-liquid annular flow, liquid film distribution, sub-flow regimes, ring island array sensor
helical cruciform fuel assembly, thermo-mechanical coupling, multi-scale volume growth, fission gas swelling, thermal creep and irradiation creep.
Corrosion particles, LBE, Deposition rate, Diffusion
Multigroup cross-sections, homogenization, transport-correction, flux-moment, Monte-Carlo, Method of Characteristics
Rough rod bundle, Numerical calculation, Analytical method, Convection heat transfer
Heat pipe nuclear reactor, Neutronics-thermal-mechanics coupling, MOOSE Multiphysics, OpenMC
two-phase flow, coherent structure, void pulsation, tight lattice bundles
fuel performance analysis code, FuSPAC, fuel behaviour under irradiation, UO2 fuel
critical heat flux, flow boiling, guide thimble, Rod bundle
Heat pipe, Micro nuclear reactor, MOOSE Multiphysics
LFR, sub-channel analysis, code validation
Fuel assembly, Fouling thickness, Nucleate boiling, Deposition rate, Grid spacers
Subchannel Analysis, Radiation Heat Transfer, Safety Analysis, Fuel Bundle Assemblies
Two-phase, Coarse-mesh, Empirical correlation, Lumped parameter, Flow regime
Helical cruciform fuel, sub-channel mixing, wire-mesh sensor, flow sweeping, mixing model
U-50Zr HCF, Multiphysics coupling, Neutron transport, Thermal hydraulics, Mechanical behavior
Swirl-vane separator, Rolling motion, Flow field, Separation performance, numerical simulation
heat pipe nuclear reactor, Brayton thermoelectric conversion system, MOOSE framework
heat pipe reactor, Brayton power conversion system, MOOSE Framework
Low flow rates, Ocean conditions, Buoyancy parameter, Overall heat transfer, Local heat transfer deterioration
Nucleation site density, Fouling layer thickness, Bubble behaviors, Boiling heat transfer, RPI boiling model
Critical Heat Flux, Rod bundle test, Machine Learning
Dislocation loop, Rafting, Irradiation damage, Dislocation dynamics
