Progress in Nuclear Energy

Article	Citations
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	211
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	178
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	163
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	160
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	137
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	124
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	75
Editorial Board	72
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	68
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	68
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	66
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	56
Analysis schemes to evaluate HELB-induced blast waves	54
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	53
Numerical study on the interface debonding effect on FCM fuel behavior	53
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	52
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	51
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	50
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	50
Detail CFD simulation of the integrated reactor pressure vessel of SMART	48
Elucidating the influences of strontium (II) oxides in TeO2–B2O3–BaO: Fabrication, Raman spectroscopy, and γ-ray protection properties for the novel high-density glasses	44
Multi-step time series prediction for nuclear power plants based on variational mode decomposition and gated recurrent units	44
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	43
Static output feedback H∞43
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	43

Surrogate modeling of heat transfer under flow fluctuation conditions using Fourier Basis-Deep Operator Network with uncertainty quantification	43
Upgrade of FROBA code to derive new insights in fuel performance of Lead-Bismuth Eutectic Cooled Fast Reactor	43
Two-group approach to develop drift-flux model for downward dispersed two-phase flows	42
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	42
Stator current-based soft sensing for blade damage diagnosis in centrifugal pumps using ensemble learning	41
Development and application of a multi-scale coupling model for dispersion plate-type fuel	41
CFD analysis of heat transfer in homogeneous and stratified corium pools for In-Vessel Retention assessment	40
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	40
Evaluation and optimization of efficiency, mass and economics of megawatt-scale space gas-cooled nuclear reactor system	39
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	38
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	38
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	37
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	36
High-fidelity microreactor load follow simulations with model predictive control	35
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	34
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	34
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	33
Simulation of the effect of partial and total blockage of a sub-channel on two-phase flow through a 5 x 5 square rod bundle	32
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	32
Thermal air oxidation of UO2: Joint effect of precursor's nature and particle size distribution	32
Experimental and theoretical investigation on the effect of surface porosity on the nucleate flow boiling heat transfer	31
Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications	31
Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test	30
Flow instability identification with a clustering-assisted tree-based machine learning framework	30
Availability assessment of a nuclear reactor limitation system by a Timed Petri Net	30
Experimental study on polydisperse aerosol removal under multi-parameter spray conditions in containment	30
Numerical research on the influence of inlet shape on the air flow and heat transfer characteristics inside the reactor channel	29
Investigation of the pulsed neutron source method measuring the fission decay properties of a subcritical assembly with low-Z reflectors	29
Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems	28
The time for revolutionizing small modular reactors: Cost reduction strategies from innovations in operation and maintenance	28
Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel	28
Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface	28
Sensitivity and uncertainty analysis of neutron activation source terms based on statistical sampling method	27
Experimental and first principles characterization of injection moulded Ti-Al-Sn-Zr-Mo alloy for nuclear applications	27
Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies	26
Effect of smectite illitization on swelling behavior of Gyeongju bentonite	25
Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR	25
Reliability Analysis of Safety-Critical Systems using Optimized Petri Nets	25
Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics	25
Effects of elevated temperature steam oxidation and subsequent quenching on light water reactor clad	25
Thermo-neutronic integrated coupling effects on nuclear reactor core calculations	25
Advanced and Small Modular Reactors’ supply chain: Current status and potential for global cooperation	25
Optimization of a NuScale-like SMR: A Master-Slave Parallel computing in Particle Swarm approach for enhancing nuclear reactor project and initial fuel cycle efficiency in seed-blanket configurations	25
Radiological characterization plan for decommissioning IFIN-HH's Cyclotron	25
A study on nuclear hydrogen production using a novel approach cobalt-chlorine thermochemical cycle in a laser driver fission fusion blanket for various molten salt fuels	25
Evaluation of advanced drift-flux correlation for predicting low-flow and low-pressure two-phase flow behaviors in rod bundles	24
Decay heat characterization for molten salt reactor concepts with power density, humidity, and air ingress as uncertain parameters	24
Prediction of core unmeasurable parameters during loss of coolant accident using deep neural network method	24
Enhancing the radiation shielding performance of polyepoxide composites based on cement bypass dust	24
Subchannel-scale CFD simulation of thermal-hydraulics in a PWR full core with mixing vane spacer grids	24

Assessment of RELAP5/SCDAPSIM code against NACIE-UP facility tests	24
Quantitative analysis of contributing factors to the resilience of emergency response organizations in nuclear power plants	24
Conceptual design of heat pipe cooled reactor with liquid sodium core for space power systems	24
Unsupervised anomaly detection for Nuclear Power Plants based on Denoising Diffusion Probabilistic Models	23
Fragility analysis of nuclear containment under inner pressure based on a simplified method and program (NCMC)	23
Study on bubble growth interphase heat transfer of rapid decompression	23
Experimental study of three-dimensional trajectory and dynamic characteristics of rising bubbles	23
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization	23
Atlas of historical and proposed nuclear devices and power systems in the Earth-Moon System and wider Solar System	22
Advances in technology, design and deployment of microreactors- a review	22
Thermal-hydraulic performance of natural circulation system with narrow rectangular channel under heaving condition based on 1D/3D coupling analysis	22
A review of structural material compatibility in sodium-cooled nuclear reactors	22
Numerical investigation on effects of fuel rod with different bow deformation ratio X on two-phase boiling and flow performances of coolant in fuel assembly	22
Deterministic and probabilistic Deep Learning in predicting reactor physics of subcritical system driven by a pulsed source	22
Neighboring country's nuclear power plant? “No, thanks”: An energy justice analysis	21
Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh	21
Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations	21
Experimental study on bubble dynamics in narrow rectangular blistering channels – Part Ⅰ: Bubble nucleation	21
A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions	21
Advanced radiation shielding methodology for small modular reactors using a multithreaded two-step source approach	20
Investigation of flow-induced vibration in core sub-assemblies of sodium-cooled fast reactors	20
Investigation of optical, mechanical, and shielding properties of zirconia glass capsule	20
Heat transfer enhancement using different Ag/GPE nanofluid mixing conditions on a downward-facing heating surface	20
Study on the influence of heating power on reflooding process in rectangular narrow channels	20
Blocked ion exchange - an innovative approach to cementing spent organic ion exchange resins	19
Simulation model for investigating safety margin of three-layer molten pool after late phase in-vessel water injection	19
Generation of nodal neutronic parameters’ library based upon high-fidelity core-wide simulations - Part I: Base model	19
Numerical approximation of a fractional neutron diffusion equation for neutron flux profile in a nuclear reactor	19
CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system	19
Large leakage sodium-water reaction accident analysis in a sodium-cooled fast reactor with paralleling steam generators	19
Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries	19
SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model	19
Multi-scale system–subchannel coupling for PWR thermal-hydraulic analysis: Development and Validation	19
Development and integration of a tool for physics-based shape and topology optimization in the MOOSE multiphysics simulation framework	19
Experimental analysis of forced convection heat transfer of Hybrid Nanofluids in a vertical annulus with cosine heat flux	19
Development of fuel depletion code for molten salt reactor with very deep burnup	19
An attempt to find the optimal loading pattern of minor actinides in the PWR fuel rods	18
Evaluation of Accident Management (AM) actions in a Westinghouse 2-loop PWR during MSGTR using best estimate approach with TRACE v5p8 code	18
Optimized fuel cycle and burnup analysis for pebble-bed reactors	18
Transient fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics method	18
Research on radiation monitoring schemes for industrial steam supply from the secondary loop of PWR	18
Verification of the NACAC atmospheric dispersion calculation using a hypothetical accident in a neighboring nuclear power plant	18
Lithium isotopic analysis in depleted lithium salts	18
Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites	18
Nonlinear vibrations analysis of a fuel rod in nuclear heating reactor	18
A study on the long-term variation of signal current in rhodium self-powered neutron detectors under in-core burnup conditions	17
Modeling a three-layer container based on halloysite nano-clay for radioactive waste disposal	17
Design of fractional-order NPID controller for the NPK model of advanced nuclear reactor	17
Numerical simulation study of liquid sodium contact angle on gradient sodium-philic nanostructure surface based on Lattice Boltzmann method for heat pipe rector application	17
Towards area-dependent, scenario-based multi-hazard models: Part B – Case studies	17
Corrigendum to ‘First-principles study of the doping mechanism of the electrochemical oxygen pump electrolyte in liquid lead-bismuth eutectic’ [Prog. Nucl. Energy, 185 (2025), 105794]	17
Preliminary neutronics optimization on the concept of multi-beam accelerator driven system	17
Bias and bias uncertainty prediction For VENUS-F reactor core configurations	17
Pilot study of response-order effects on survey on young Chinese's perceptions of nuclear power	17
Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC	17
Uranium removal in aqueous solution by different sizes of commercial Fe3O4 microparticles: key role of oxygen vacancies	17
Experimental study and software simulation of air-water periodic flooding in a 3×3 bundle channel	17
Transient characteristics of supercritical carbon dioxide Brayton cycle system with or without control strategy under accident conditions	16
Investigating citizens’ support for the emerging innovation of nuclear microreactors	16
Transformation of montmorillonite under thermal-saline conditions in HLW repositories: A systematic review	16
CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties	16
Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX	16
Neutron sensitivity and uncertainty analysis of rhodium self-powered neutron detectors for reactor monitoring in HPR1000	16
Study of the behavior of cesium and strontium in co-melting basalt and silica gel containing cesium or strontium nitrates for the development of a potential material for radioactive waste immobilizati	16
Nuclear accident source term inversion based on explainable machine learning methods	16
Research on the radioactive safety of industrial steam supplied by PWR nuclear power plant	16
Radiometric techniques for the detection and assessment of tritium in aqueous media - a review	16
Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident	16
Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications	16
CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel	16
Assessment of neutronics performance of U3Si, U3Si2, and U–9Mo fuels for the support of MNSR conversion using SCALE 6.2.3 computational tools	16
Experimental study on startup performance of sodium heat pipe with high ratio of length-to-diameter under different coolant flow rates	16
Meso-scale numerical analysis for transport and deposition behaviors of radioactive aerosols under severe nuclear accident	16
Assessment of interfacial area model for two-phase flows in rod bundles implemented in RELAP5 code	16
Analysis of unprotected loss of flow accident in a sodium cooled fast reactor using coupled thermal hydraulics neutronics code ASTRA	15
Investigating the effects of natural gas, nuclear energy, and democracy on environmental footprint and energy risk in France: Does financial inclusion matter?	15
Modification of the turbulent model for flow in bare rod bundle based on data assimilation technology	15
Design and simulation of neutron radiography system for an aqueous homogeneous solution reactor	15
Prediction and analysis of decay heat transfer in the core of the pebble bed reactor	15
Experimental research on the two-phase turbulent mixing between rod bundle subchannels with spacer grid	15

Hybrid IACO-A*-PSO optimization algorithm for solving multiobjective path planning problem of mobile robot in radioactive environment	15
Linked calculation method based on next event estimation for directional shielding problems	15
Uncertainty estimation of bifurcated solutions in the Rayleigh–Bénard problem for advanced nuclear reactors applications	15
Onset and evolution of counter-rotating baroclinic vortex pair in shock induced aerobreakup of droplets	15
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign	15
Editorial Board	15
Application of similarity analysis method in neutronics design of multi-purpose experimental reactor	15
Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor	15
A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay	15
Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling	14
Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE	14
Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation	14
A First collision source method using spherical harmonics method for arbitrary shape and order finite element mesh	14
Adaptive BP-PID control for steam generator level using hardware-in-the-loop simulation	14
Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies	14
Review of melt-coolant interaction phenomenon in liquid metal cooled reactors: studies on low-temperature coolant impinging into high-temperature melt pool	14
Equivalence method and transient flow characteristics of the integrated valve	14
Development of a liquid metal subchannel code applied to ocean conditions and study on the effect of core geometry parameters and ocean motions on flow and heat transfer characteristics	14
Regenerating and estimating missing parameters in critical benchmark experiments: A framework for inverse uncertainty quantification using information-theoretic experiment design	14
Investigation on aerosol removal by spray droplets under severe accident conditions	14
Analysis of UO2, UN and U–10Zr fuels burning in a MegaPower reactor with solid monolithic and independent fuel element core designs	14
Effect of H and Pd atoms on the migration of He atoms in 3C–SiC	14
Hydrogen risk analysis in small containment with a pressure suppression tank	14
Optimization of synthesis conditions for preparation of radiation grafted polymeric fibers and process variables of adsorption with response surface methodology	14
Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks	14
Mitigating medium break loss of coolant accidents: Optimizing control system setpoints using genetic algorithms	14
Numerical simulation study on the filtration performance of metal fiber filters	14
A molecular-kinetic theory based model for alkali liquid metal boiling incipience analysis	14
Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties	14
Security measurement of instrumentation systems: A case study of NPP	14
Experimental and numerical study of particle resuspension on turbine surface with film cooling	14
Measurement of helium thermophysical properties and modification of the calculation models in the KTA 3102.1 report	14
Analysis on the influence of protection electrodes on the capacitance control rod position sensor	14
Interfacial behaviors, kinetic analysis and dynamic parameters of disturbance waves in 3 × 3 rod bundle channels	14
Experimental and theoretical studies (DFT) on technetium extraction as HTcO4 using dicyclohexano-18-crown-6 in a blend of isodecyl alcohol and n-dodecane from acidic medium	14
Experimental study and numerical simulation on hydro-dynamic characteristics of cylindrical floating nuclear power platform	14
Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite	13
The economics of nuclear propulsion for containerships	13
Investigation of hybrid nanofluids effects on heat transfer characteristics in VVER-1000 nuclear reactor	13
Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel	13
Electrochemical decladding of used nuclear fuel	13
A novel automated thickness measurement method and device for nuclear fuel plates	13
Development of a practical control-oriented mathematical model for gas pressurizer	13
Data-driven hierarchical coordinated decoupling control of a heat pipe reactor-SCO2 system	13
Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids	13
The technology of shielding design for nuclear reactor: A review	13
Study on the condensation oscillation characteristics of steam-seawater low-velocity jet	13
An intelligent active fault tolerant control strategy for pressurized water reactor: Addressing sensor faults	13
Numerical modelling of catalytic hydrogen combustion in passive autocatalytic recombiners: A review	13
Experimental and numerical study of single bubble migration behavior in stagnant molten LBE	13
Experiment investigation of a secondary PRHR cooling effect on an integral facility after a LOCA accident	13
Flow distribution characteristics of parallel narrow rectangular channels under deformation conditions -Part I: An experimental study	13
Causative process related method for the design of a reduced scale test facility for boron dispersion analysis in the pressurizer of SMRs	13
Multi-step prediction of main pump leakage in nuclear power plants with an additive model	13
Availability analysis of safety-critical systems of nuclear power plant using ordinary differential equations and reachability graph	13
Investigation of radiation shielding properties of basalt-based glasses: Binodal/Spinodal decomposition effect theory	13
The potential of bi2–xZrxO3+x/2@ZrO2 (BZO) as a heavyweight radiation shielding material: Fabrication and characterization using a hydrothermal technique directly from zircon mineral	13
Detailed transient modeling and FPGA-based real-time digital-twin development for sodium-cooled fast reactor	13
Impacts of climate extremes on nuclear power plants in Canada, the United States (U.S.), and France	13
The Lagrangian particle-based simulation of finned freeze plugs melting in the molten salt reactor	13
Evaluating local wind circulation metrics for radionuclide transport and dispersion: A practical approach for radiological safety	13
RHR water intake pipeline special hydraulic phenomenon test verification	13
Multi-physics coupling simulation of an electrorefiner for pyroprocessing of spent nuclear fuel	13
Development of an improved turbulent heat flux model for the heat transfer of supercritical fluids	13
Numerical investigation of flow dynamics and performance in a supercritical CO2 ejector: Effects of geometric parameters and operating conditions	12
Effect of strontium and cesium on corrosion and contamination of 316L stainless steels during spent nuclear fuel reprocessing	12
Experimental and numerical analysis of sloshing in annular sectored containers under tangential direction excitation	12
Chemical states and reactions in multicomponent and multiphase systems containing different nuclide quantities	12
Review of researches on flow blockage accident in liquid-metal-cooled reactor	12
Can BRICS economies shift some burden on nuclear energy efficiency for sustainable environment? An empirical investigation	12
Research on internal flow characteristics of gas-liquid two-phase flow in reactor coolant pump	12
Experimental study on the “double peaks” heat transfer characteristics of supercritical carbon dioxide	12
Evaluating the performance of passive second-stage hydro accumulators to enhance safety margins at Bushehr NPP	12
Role of Sm3+ ions as network-modifying on elastic, mechanical, and radiation shielding properties of MgO–B2O3–TeO2 glasses	12
Study on flow heat transfer characteristics and mechanism of lithium-lead and helium-xenon	12
Characterization of plasma catalytic system degradation of low concentration 14CH4	12
Using advanced machine learning techniques to improve equipment health monitoring in NPPs	12
A losses and hazards identification process (LHIP) when connecting an additional system	12
Experimental research on thermal-hydraulic characteristics of generation Ⅲ PWR under LOCA conditions	12
A review on properties required for FB-CVD fabricated SiC for TRISO fuel production	12
Effect of Ni2+ and Cr3+ on electrodeposition of uranium dioxide in LiCl–KCl molten salt	12
Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture	12
LOFA and LOUHS analysis on the energy well SMR using TRACE code	12
Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures	12
Designing a molten core collection chamber for Bushehr-1 nuclear power plant using MELCOR 1.8.6 and ANSYS-FLUENT codes	12
Research on fluctuation attenuation and optimization of passive residual heat removal system based on spring vibrator	12
Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel	12
Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids	12
Supercritical carbon dioxide critical flow model based on deep learning	12
Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review	12
Research on the influence mechanism of non-uniform inflow on the pressure pulsation of the Reactor Coolant Pump	12
Development of thermo-physical property database and code of fusion materials for CFETR blankets	12
Experimental study on convective heat transfer of S–CO2 under high heat flux	12
Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the RELAP5 code and Computa	12
Effect of surface preparation on corrosion of Zr-2.5Nb alloy in high temperature Steam-LiOH environments	11