Progress in Nuclear Energy

Papers
(The TQCC of Progress in Nuclear Energy is 5. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-04-01 to 2025-04-01.)
ArticleCitations
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9272
An efficient method for solving flow field in high temperature gas-cooled reactor174
Study of oxide and α-Zr(O) growth kinetics in the temperature range 1000–1500 °C during steam oxidation of Indian PHWR cladding172
Design and optimization of a 500 kW multi-cylinder double-acting free piston stirling engine for deep-sea nuclear power system138
Analysis of core quality criteria and requirements for high-level waste disposal R&D based on the US NQA-1 and Korea KEPIC-QAP99
Analysis schemes to evaluate HELB-induced blast waves97
Experimental study of the dominant frequency of pressure oscillations and condensing pattern in vertically upward steam bubbles jets under rolling conditions95
Novel burnup measurement system via anti-compton techniques for HTR-1092
A rapid approach to generate multi-unit event trees based on tree combinatorial calculation92
Application of response surface methodology for modeling and optimization of the extraction and separation of Se(IV) and Te(IV) from nitric acid solution by Cyanex 301 extractant91
Effect of certain metrological parameters on the extension of urgent protective action zone in Tehran research reactor accidents83
Co-dimension two bifurcations of limit cycles starting from generalized Hopf bifurcation for the dynamical system of nuclear reactors78
Stability and bifurcation analysis of Generation IV reactors via point reactor models with temperature reactivity feedback78
Feasibility studies on the detection of third phase formation in the solvent extraction equipment during reprocessing of fast reactor spent fuels73
Characteristics of bubbles swimming in different liquid regions of the slug flow in vertical and inclined rectangular channel72
A meta-heuristic algorithm based on Henry's law for the load-following of a two-point PWR model68
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher64
Column percolation leaching test for rare-earth processed residue: Standard laboratory column elution experiments towards development permanent disposal facility (PDF)62
Experimental study on performance optimization for full-scale swirl separator of air-water in PWR UTSG58
DYSN: Dynamics simulator for the NuScale SMR - A mathematical framework for transient analysis51
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor51
Editorial Board51
A novel approach of precipitation of Ammonium Di -Uranate (ADU) by sonochemical route47
Non linear stability analysis of supercritical water cooled reactor: Parallel channels configuration46
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade46
Predicting reverse flow characteristics in equal-height-difference passive heat removal system for ocean nuclear power45
Thermal hydraulic stability analysis of supercritical water-cooled reactor under the effect of seismic-wave acceleration39
Editorial Board39
Simulating the erosion modelling of pipes used in nuclear power plants in terms of physical decontamination38
Research on equipment survivability assessment in severe accidents for CANDU637
Status, opportunities, and challenges of nuclear power development in Sub-Saharan Africa: The case of Ghana37
Structure and gamma-ray attenuation capabilities for eco-friendly transparent glass system prepared from rice straw ash37
Optimize the design analysis of hybrid fin structure microchannel heat exchanger36
A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units36
Investigation of the source term and radiological consequences of small break LOCA with failure of the emergency core cooling system in Bushehr nuclear power plant36
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement35
Influence of solid electrolyte material selection on electromotive force characteristics of oxygen sensor for lead-cooled fast reactor35
CFD simulation and flow-induced vibration evaluation of PWR steam generator U tubes34
Performance improvement in temperature thermometry using data analytics - A nuclear power plant perspective33
Dynamic mode decomposition coupled with multilevel octree grid algorithm for large-scale discrete ordinates neutron transport calculations33
Investigating the influence of the variation of the load characteristic on the occurrence frequency of Grid-related Loss of Offsite Power using a probabilistic-deterministic methodology33
Numerical study on migration and solidification behavior of molten droplets on structure surface and in debris voids during debris bed melting process32
Fractional neutron point kinetics model for reactivity transients of the NuScale and comparison with the classical kinetics approach32
Evaluation of U3O8–Al, UO2–Zr, and U3Si2–Al fuel plates in a hypothetical melting accident of Tehran research reactor (TRR)32
Adaptive backstepping controller with extended state observer for load following of nuclear power plant31
Numerical study of the effect of geometry on the behaviour of internally heated melt pools for in-vessel melt retention31
Evaluation of time dependent neutron transport algorithms using 2D modular ray tracing MOC30
Impact of source term release characteristics of nuclear plant on the performance of EURDEP to identify radioactive plumes30
Editorial Board30
Temperature dependence of Cs release during oxidation of Cs-loaded graphite30
Effects of casting parameters and impurity concentrations on as-cast U–10Mo29
Vortex shedding induced vibration of thin strip in confined rectangular channel28
Editorial Board28
The computational fluid dynamics evaluation of the diffuser on N-16 radioisotope rise time in TRIGA mark II research reactor tanks28
Numerical investigation on critical heat flux for 5 × 5 fuel assemblies with a wide range of working conditions28
Inter-comparison of transboundary atmospheric dispersion calculations: A summary of outputs from the ASEAN NPSR benchmark exercise28
Reliability and availability simulation for vessel cooling system of the high temperature engineering test reactor27
Editorial Board27
Editorial Board27
Editorial Board27
Experimental study of insoluble aerosol wash-down by condensate on quasi-horizontal plate27
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area26
Nuclear fuel cycle–related R&D classification for implementing the IAEA's additional protocol26
Modeling of mass transfer coefficient using response surface methodology in a horizontal-vertical pulsed sieve-plate extraction column25
Predicting degradation of organic molecules in cementitious media25
Advances in time-dependent Monte Carlo simulations for void velocity determination using neutron noise techniques25
Efficiency analysis of multiple detector effects on MCNP 6.2 simulations25
Comprehensive assessment of radiation impact from natural radioactivity and tritium around Rooppur NPP before commissioning and predicted exposures of NPP operation24
Numerical investigation of gas-liquid two-phase flow in horizontal pipe with orifice plate24
Identification of the Fe3<23
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results23
Prioritizing pressure drop research in nuclear thermal hydraulics23
Detailed comparison of the characteristics of mixing and subchannel vortex induced by different spacer grids23
Acoustic characterization study for multi-hole orifices in nuclear piping system22
Elucidating the influences of strontium (II) oxides in TeO2–B2O3–BaO: Fabrication, Raman spectroscopy, and γ-ray protection properties for the novel high-density glasses22
Experimental investigation of emulsion phase holdup in uranium extraction with emulsion liquid membrane technique by a pulsed packed extraction column22
Experimental study on the influence of gas injection on flashing in open natural circulation systems under stable boundary conditions22
Numerical simulation of aerosol generation by cutting fuel debris and aerosol removal by spray droplets during Fukushima decommissioning21
Li2B4O7–Bi2O3–ZrO4–CaWO4 glass system for neutron protection in neutron applications21
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition21
The research challenges in security and safeguards for nuclear fission batteries21
Experimental investigation of aluminum fins on relative thermal performance of sintered copper wicked and grooved heat pipes21
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield20
Optimization of an ejector to mitigate cavitation phenomena with coupled CFD/BP neural network and particle swarm optimization algorithm20
An optimal plate-fin heat exchanger design using opposition-based Orthogonal Learning Kho-Kho Optimization algorithm20
Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions20
Optical and gamma-ray shielding properties of calcium sodium borate glasses with varied equal concentrations of ZnO and BaO20
Use of hybrid resin to reduce silica from spent fuel pool borated water of power plant at pilot scale20
Radiation shielding performances of Na2SiO3 based low-cost micro and nano composites for diagnostic imaging20
Derivative dynamic time warping algorithm with introduced correction for varying load fault diagnosis of nuclear power system steam turbine units19
Development and validation of a neutron transport solver with S19
Main lessons learnt from 40 years of R&D on iodine source term prediction: Identification of the main parameters governing iodine volatility in PHEBUS FP tests19
Investigation on heat transfer characteristics of Pb–Bi/S–CO2 PCHE with different channel structures19
Engineering multifunctional polypropylene nanocomposites: Tailoring structural, thermal, and gamma-ray shielding properties with Ni0.9Zn0.1Fe2O4 doping19
Investigation on the effect of low aspect ratio on heat transfer characteristics for light metallic layer19
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct18
Research and optimization design of buffer protection in passive shutdown subassemblies18
Investigation of air-water two-phase flow characteristics in a 25.4 mm diameter circular pipe18
Simulation of activated corrosion product activity in Korean design system-integrated modular advanced reactor (SMART) under steady-state flow and linearly accelerated corrosion18
Development and validation of a two-fluid three-field model for the vertical upward flow18
Heat transfer of film boiling on the molten metal after water injection18
The burnup raising feasibility by studying the effects of Th and U contents on the thermophysical and mechanical properties of Th1-xUxO2 solid solutions18
Theoretical analysis on bubble radius and pressure fluctuation during steam bubble condensation18
Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software18
Oxidative decomposition of ammonium ion with ozone in the presence of cobalt and chloride ions for the treatment of radioactive liquid waste18
Analysis of the PHWR benchmark transient using a high-order spherical harmonics-nodal collocation method and treatment of rod cusping effect18
Assessment of advanced boiling flow and heat transfer models for PHWR conditions17
Pilot numerical study of new design of passive residual heat removal heat exchanger tubes17
“Qualitative and time analysis of the gaseous constituents transport processes in a micro-tunnel on the basis of in-situ measurements”17
Fission source stationarity diagnostics using the Fourier fundamental mode coefficient17
Computational case study on upward two-phase flow in vertical circular pipe based on CFD approach: Multidimensional flow instabilities investigation17
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors17
An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach16
Numerical analysis of safety of a borehole repository for vitrified high-level nuclear waste16
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control16
Assessment of chlorination technique for decontamination of radioactive concrete waste using simulated concrete waste16
The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs16
Experimental study on fine particle deposition in supercritical water natural circulation16
Static output feedbackH16
Eigenvalues of the neutron transport equation in X16
Imaging multi-materials tightly combined objects by applying grey relational analysis in muon tomography16
Deterministic and stochastic methods for sensitivity analysis of neutron noise16
Method for measuring the saturated permeability coefficient of compacted bentonite at temperatures exceeding 100 °C16
Separate-effect drainage tests in a core make-up tank16
Single-phase density wave oscillation -A new phenomenon of flow instability in inverted U-Type Steam Generator16
Characteristics and optimation of heat pipe radiator for space nuclear propulsion spacecraft15
Quantification of the 35Cl(n,15
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods15
Numerical study on subcooled flow boiling in narrow rectangular channel based on OpenFOAM15
Turbulence dissipation of leakage flow in supercritical CO2 labyrinth seals15
Modeling of turbulent diffusion terms for one-dimensional interfacial area transport equation in vertical round channels15
Numerical simulation on flow and reaction characteristics for catalytic region in helium-heated steam reformer coupled with HTR-1015
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis14
Research on purge gas flow characteristics in different pebble bed structures for fusion blanket14
SIMMER code two-fluid model well-posedness and stability for simulating liquid metal (lead–lithium eutectic), water vapor, and non-condensable gases multi-component multi-phase flows14
A tree-based automated machine learning approach of the obstructed view factor of thermal radiation in nuclear pebble beds14
Radiological safety evaluation of a recycling facility for dismantled concrete waste14
Comparison of different approaches for numerical modeling of nanofluid subcooled flow boiling and proposing predictive models using artificial neural network14
A combined strategy for dynamic probabilistic risk assessment of fission battery designs using EMRALD and DEPM14
Research on a two-phase condensation model with predictable turbulent film14
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger14
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations14
Emergency evacuation time model of nuclear power plant pedestrians14
Separation characteristics analysis and optimization design of AP1000 wave type separator14
Fluence calculations for the TRISO- particle fuel ION implantation experiment14
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor14
Numerical simulation of SMILE core bypass narrow-slit flow characteristics under power operation conditions14
Preliminary code development for single-phase liquid natural circulation flow simulation based on two-phase compressible model14
A flexible nuclear energy system using cryptoassets as enablers: Economic assessment13
Analysis of the radioactivity in bio-shield of Kori NPP unit 1 via computational simulation13
Measurement of mass attenuation coefficient and its derivable in polymers13
Experiment study on the flow mechanism of the molten pool relocation using simulant materials at room temperature13
Numerical simulation of melt jet breakup under non solidification conditions13
Role of structure and organic contaminants on Cs Sorption by clays13
Process flowsheet test of the i-SANEX process with CHON-compliant ligands in aqueous and organic phases13
Editorial Board13
Detail CFD simulation of the integrated reactor pressure vessel of SMART13
Analytical modeling of bentonite swelling with experimental validations through hydrothermal reaction and free swelling index measurement13
Effect of irradiation on thermal stability of nitric acid solutions of acetohydroxamic acid13
Supercharging performance of anti-cavitation schemes in pool-type reactor: Experimental verification and numerical investigation13
Release of windowed multipole library for ENDF/B-VIII.0 in support of OpenMC criticality and depletion analysis13
Investigation of pressure and temperature variations and flow pattern evolution during pressurized water injected into lead-bismuth eutectic13
Removal of bond sodium from Fermi-1 blanket assemblies using a melt-drain-evaporate process13
A hybrid Analytical Discrete Ordinates-Response Matrix Constant Nodal method for one-speed X, Y-geometry transport problems13
Autonomous control of heat pipes through digital twins: Application to fission batteries13
Research on power regulation and distribution of the improved NHR200-II low temperature nuclear heating reactor13
Physical optimization and safety analysis of space thermionic reactor13
UTOP accident analysis and mitigation measures of lead-cooled fast reactor considering coupling effect with SCO2 Brayton cycle12
An adaptive navigation model for path finding in radioactive environment12
An enhanced mathematical model for evaluating grid-to-rod fretting wear under complex boundary12
Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model12
The instability marsh phenomenon and marginal stability boundary distortion of density wave oscillation in parallel channels12
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor12
Theta method applied to two-energy groups point kinetics equations12
Prediction of sodium leakage droplet size distribution in sodium-cooled fast reactor loop12
Experimental study of IVR-ERVC CHF limits for CAP140012
Neutronic design analysis of CEA Cadarache URANIE subcritical assembly12
Control of small pressurized water reactors under single-loop operation based on MFAPC theory12
Interaction behaviour of alloy 690 upon exposure to P2O5 containing borosilicate glass at simulated vitrification conditions12
Multi-gene genetic programming of critical boron concentration and power peak factor for nuclear reactor fuel reload calculations12
Experimental simulation of selected design extension condition scenarios without core meltdown in the CODEX facility12
Dry-out characteristics of debris bed under different water injection conditions12
Enhanced PAUT method with pulse compression for heavy-walled CASSs in nuclear power plants12
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Unknown fault detection12
Experimental study on coupled quenching behavior in a dual-cooled annular rod channel12
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR12
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax12
Performance analysis of indirect contact heat pipe radiator for space nuclear power system12
Vulnerability learning of adversary paths in Physical Protection Systems using AMC/EASI11
High volume packing fraction TRISO-based fuel in light water reactors11
Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal11
Shutdown dose rate calculation for fission reactors: An application of the MS-CADIS method to OPAL11
Thermal-hydraulic analysis of helical coil once-through steam generators under complex oceanic conditions11
Application of Lie symmetry to find an analytical solution for reactor point kinetics equation with prompt jump approximation and power feedback11
A multi-level fuzzy switching control method based on fuzzy multi-model and its application for PWR core power control11
CHF enhancement of CNT-COOH nanofluids in the boiling experiment with a downward-facing heating surface11
Radiotoxicity analysis of the spent nuclear fuel of VVER-1200 reactor11
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model11
Investigating the applicability of human reliability analysis methods during early design stages of non-light-water nuclear power plants11
Experimental study on effect of pressure on ADS-4 liquid entrainment characteristics in T-junction11
Improvements of the dynamics code TMSR3D for molten salt reactor leveraging triangular prism nodal method11
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects11
Method for control drum position critical search with Monte Carlo codes11
Oxidation of molten zirconium-containing droplet in water11
Investigation of Monte Carlo trained CNNs for neutronics predictions of typical and atypical PWR assemblies11
Research on sensor condition monitoring and signal reconstruction based on self-correcting anomaly diagnosis model11
Study on non-uniform circumferential temperature distribution of annular fuel in the tight lattice configuration of a lead-bismuth cooled fast reactor11
Study on the most severe condition for structural assessment of nuclear fuel transport package under impact loading11
Contact phenomena between load-bearing skeletons of bowed fuel assemblies in PWRs with mixed cores11
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior11
Experimental and model development of lead-bismuth eutectic solidification phenomenon flowing inside the tube10
Modified austenitic stainless-steel alloys for sheilding nuclear reactors10
Microstructure transformation of Mo–3Nb single crystal used for space thermionic reactor during welding10
Design of optimal fractional order fuzzy PID controller based on cuckoo search algorithm for core power control in molten salt reactors10
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review10
Investigating the possibility of using a mixture of thorium with different fissile materials as a fuel in TRISO particles for the PBMR-400 reactor10
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle10
Seismic fragility analysis of containment structure subjected to near fault ground motions10
Numerical investigation on boiling crisis characteristic of a 7-rod HCF assembly in hexagonal lattice10
Effects of PVB addition on PbO ceramics used in lead-cooled fast reactors10
A Takagi Sugeno based reactor power control of VVER-1000 using linear parameter varying identification of two-point kinetic model10
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor10
Recent progress in CdZnTe based room temperature detectors for nuclear radiation monitoring10
Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations10
Editorial Board10
Comparison and analysis of combustion characteristics and interference effect between single burning sodium jet and the dual-jets10
Potential of electrolytic processes for recovery of molybdenum from molten salts for 99Mo production10
Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors10
Nuclear radiation shielding characteristics and physical, optical, mechanical, and thermal properties of lithium-borotellurite glass doped with Rb2O10
Study of density wave instability in natural circulation with parallel channels under inclined and heaving conditions10
Core flow distribution optimization of a natural circulation reactor using genetic algorithm, simulated annealing and characteristic statistic algorithm10
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method10
A comprehensive research on γ-ray and particle radiation interaction parameters of Cerium doped heavy oxide inorganic scintillators9
Experimental and FLUKA evaluation on structure and optical properties and γ-radiation shielding capacity of bismuth borophosphate glasses9
Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM9
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods9
Evaluating the impact of airborne radionuclides caused by the Fukushima nuclear accident on China based on global atmospheric dispersion9
Simplified-DP9
Review of nuclear microreactors: Status, potentialities and challenges9
A review of multiphysics tools and methods to evaluate high temperature pebble bed reactors9
Dynamic simulation of a space lithium-cooled reactor system coupled with a He–Xe closed Brayton cycle9
Safety analysis of a supercritical carbon dioxide cooled reactor system coupled with Brayton cycle under loss-of-coolant accident9
Multi-objective optimization and configurations comparison of closed-air Brayton cycle9
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel9
A survey of multi-objective optimization methods and their applications for nuclear scientists and engineers9
Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT19
Study on the difference between B4C powder and B4C pellet regarding the eutectic reaction with stainless steel9
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites9
Mass optimization of a recompression supercritical nitrous oxide and helium power system for space exploration9
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics9
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