Progress in Nuclear Energy

Article	Citations
High-fidelity microreactor load follow simulations with model predictive control	317
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	266
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	197
Analysis schemes to evaluate HELB-induced blast waves	159
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	132
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	126
Eigenvalues of the neutron transport equation in X–	125
Static output feedback H∞108
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	107
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	81
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	79
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	76
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	64
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	59
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 extractant	56
Research on equipment survivability assessment in severe accidents for CANDU6	55
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	55
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	52
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	51
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	50
Stator current-based soft sensing for blade damage diagnosis in centrifugal pumps using ensemble learning	49
Numerical study on the interface debonding effect on FCM fuel behavior	46
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	44
Surrogate modeling of heat transfer under flow fluctuation conditions using Fourier Basis-Deep Operator Network with uncertainty quantification	43
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	43

Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	43
Multi-step time series prediction for nuclear power plants based on variational mode decomposition and gated recurrent units	42
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	41
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	41
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	40
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	39
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	38
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	38
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	38
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	38
Detail CFD simulation of the integrated reactor pressure vessel of SMART	37
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	37
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	36
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	36
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	35
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	35
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel	34
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	34
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	34
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	33
Thermal-hydraulic performance of natural circulation system with narrow rectangular channel under heaving condition based on 1D/3D coupling analysis	33
Study on bubble growth interphase heat transfer of rapid decompression	32
Thermo-neutronic integrated coupling effects on nuclear reactor core calculations	31
Fragility analysis of nuclear containment under inner pressure based on a simplified method and program (NCMC)	30
Experimental study on bubble dynamics in narrow rectangular blistering channels – Part Ⅰ: Bubble nucleation	30
Numerical research on the influence of inlet shape on the air flow and heat transfer characteristics inside the reactor channel	30
Experimental and first principles characterization of injection moulded Ti-Al-Sn-Zr-Mo alloy for nuclear applications	30
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	30
Deterministic and probabilistic Deep Learning in predicting reactor physics of subcritical system driven by a pulsed source	29
Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics	29
Editorial Board	28
Experimental estimates of hygroscopic growth of particulate fission product species (mixed CsI–CsOH) with implications in reactor accident safety research	28
Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies	28
Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR	27
Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces	27
Separation anion and cation exchange resins using fluidization and adjusted NaOH solution density methods	27
Investigation of the pulsed neutron source method measuring the fission decay properties of a subcritical assembly with low-Z reflectors	27
Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison	27
Experimental study on polydisperse aerosol removal under multi-parameter spray conditions in containment	26
Experimental and theoretical investigation on the effect of surface porosity on the nucleate flow boiling heat transfer	26
Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel	26
Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications	25
Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test	25
Scaling deep learning for whole-core reactor simulation	25
Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface	25
Atlas of historical and proposed nuclear devices and power systems in the Earth-Moon System and wider Solar System	25
Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems	25
Reliability Analysis of Safety-Critical Systems using Optimized Petri Nets	24
Thermal air oxidation of UO2: Joint effect of precursor's nature and particle size distribution	23
Quantitative analysis of contributing factors to the resilience of emergency response organizations in nuclear power plants	23

Advanced and Small Modular Reactors’ supply chain: Current status and potential for global cooperation	23
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	23
Effects of elevated temperature steam oxidation and subsequent quenching on light water reactor clad	23
A detailed design for a radioactive waste safety management system using ICT technologies	23
Conceptual design of heat pipe cooled reactor with liquid sodium core for space power systems	23
Radiological characterization plan for decommissioning IFIN-HH's Cyclotron	22
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization	22
Enhancing the radiation shielding performance of polyepoxide composites based on cement bypass dust	22
Effect of smectite illitization on swelling behavior of Gyeongju bentonite	22
The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks: An experimental study	22
Experimental study of three-dimensional trajectory and dynamic characteristics of rising bubbles	22
Advances in technology, design and deployment of microreactors- a review	22
Sensitivity and uncertainty analysis of neutron activation source terms based on statistical sampling method	21
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	21
Assessment of RELAP5/SCDAPSIM code against NACIE-UP facility tests	21
Unsupervised anomaly detection for Nuclear Power Plants based on Denoising Diffusion Probabilistic Models	21
Revealing the nexus between nuclear energy and ecological footprint in STIRPAT model of advanced economies: Fresh evidence from novel CS-ARDL model	20
Neighboring country's nuclear power plant? “No, thanks”: An energy justice analysis	20
Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations	20
Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh	20
The time for revolutionizing small modular reactors: Cost reduction strategies from innovations in operation and maintenance	20
Research on the radioactive safety of industrial steam supplied by PWR nuclear power plant	20
Study on the influence of heating power on reflooding process in rectangular narrow channels	20
Prediction of core unmeasurable parameters during loss of coolant accident using deep neural network method	20
Availability assessment of a nuclear reactor limitation system by a Timed Petri Net	20
A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions	20
An attempt to find the optimal loading pattern of minor actinides in the PWR fuel rods	20
Pilot study of response-order effects on survey on young Chinese's perceptions of nuclear power	19
Editorial Board	19
Transient fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics method	19
CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system	19
Preliminary neutronics optimization on the concept of multi-beam accelerator driven system	18
Simulation model for investigating safety margin of three-layer molten pool after late phase in-vessel water injection	18
Optimized fuel cycle and burnup analysis for pebble-bed reactors	18
Meso-scale numerical analysis for transport and deposition behaviors of radioactive aerosols under severe nuclear accident	18
Development of fuel depletion code for molten salt reactor with very deep burnup	18
Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries	18
Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX	18
Low-temperature heat capacities for EMoO4 (E=Mg, Sr, Ba) substances formed in nuclear fuel waste glasses	18
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]	18
CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties	18
A Newton-Krylov method with dense row decomposition for steady-state neutronics/thermal-hydraulics problems	18
Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC	18
Radiometric techniques for the detection and assessment of tritium in aqueous media - a review	18
Nuclear accident source term inversion based on explainable machine learning methods	18
Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident	18
A state-aware adaptive pathfinder for dynamic minimum dose path planning during an emergency in a complex radioactive environment	17
Experimental analysis of forced convection heat transfer of Hybrid Nanofluids in a vertical annulus with cosine heat flux	17
Research on radiation monitoring schemes for industrial steam supply from the secondary loop of PWR	17
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	17
Development and integration of a tool for physics-based shape and topology optimization in the MOOSE multiphysics simulation framework	17
Evaluation of Accident Management (AM) actions in a Westinghouse 2-loop PWR during MSGTR using best estimate approach with TRACE v5p8 code	17
Nonlinear vibrations analysis of a fuel rod in nuclear heating 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	16
Verification of the NACAC atmospheric dispersion calculation using a hypothetical accident in a neighboring nuclear power plant	16
Design of fractional-order NPID controller for the NPK model of advanced nuclear reactor	16
SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model	16
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign	16
Investigating the effects of natural gas, nuclear energy, and democracy on environmental footprint and energy risk in France: Does financial inclusion matter?	16
Experimental research on the two-phase turbulent mixing between rod bundle subchannels with spacer grid	16
Analysis on waterproofing design in CCS pump building of PWR under main feed water pipe broken accident	16
The development of high temperature heat-pipe transient model for system analysis of heat pipe cooled microreactor	16
Numerical study of hydraulic fragmentation of melt jet in coolant: Breakup length and melt-coolant contact area	16
Lithium isotopic analysis in depleted lithium salts	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	15
Numerical approximation of a fractional neutron diffusion equation for neutron flux profile in a nuclear reactor	15
Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites	15
Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels	15
Investigation of flow-induced vibration in core sub-assemblies of sodium-cooled fast reactors	15
Uranium removal in aqueous solution by different sizes of commercial Fe3O4 microparticles: key role of oxygen vacancies	15
Experimental study on startup performance of sodium heat pipe with high ratio of length-to-diameter under different coolant flow rates	15
A world's dilemma ‘upon which the sun never sets’: The nuclear waste management strategy (part IV): Spain, Switzerland, Taiwan, Ukraine, and United Arab Emirates	15
Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications	15
Numerical and experimental study on natural convection outside tube bundle under small convection temperature difference	15
Uncertainty analysis of HPR-1000 LOCA with probabilistic and deterministic methods	15
Large leakage sodium-water reaction accident analysis in a sodium-cooled fast reactor with paralleling steam generators	15
Heat transfer enhancement using different Ag/GPE nanofluid mixing conditions on a downward-facing heating surface	15
3-D gamma dose rate reconstruction for a radioactive waste processing facility using sparse and arbitrarily-positioned measurements	15
Hybrid IACO-A*-PSO optimization algorithm for solving multiobjective path planning problem of mobile robot in radioactive environment	15
Assessment of interfacial area model for two-phase flows in rod bundles implemented in RELAP5 code	15

Analysis of unprotected loss of flow accident in a sodium cooled fast reactor using coupled thermal hydraulics neutronics code ASTRA	14
Modification of the turbulent model for flow in bare rod bundle based on data assimilation technology	14
Regenerating and estimating missing parameters in critical benchmark experiments: A framework for inverse uncertainty quantification using information-theoretic experiment design	14
Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks	14
Neutron sensitivity and uncertainty analysis of rhodium self-powered neutron detectors for reactor monitoring in HPR1000	14
CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel	14
Investigation of optical, mechanical, and shielding properties of zirconia glass capsule	14
Design and simulation of neutron radiography system for an aqueous homogeneous solution reactor	14
Mitigating medium break loss of coolant accidents: Optimizing control system setpoints using genetic algorithms	14
Linked calculation method based on next event estimation for directional shielding problems	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
Modeling a three-layer container based on halloysite nano-clay for radioactive waste disposal	14
CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle	14
An intelligent active fault tolerant control strategy for pressurized water reactor: Addressing sensor faults	14
Study on the condensation oscillation characteristics of steam-seawater low-velocity jet	14
Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies	14
Numerical modelling of catalytic hydrogen combustion in passive autocatalytic recombiners: A review	14
Interfacial behaviors, kinetic analysis and dynamic parameters of disturbance waves in 3 × 3 rod bundle channels	14
Transient characteristics of supercritical carbon dioxide Brayton cycle system with or without control strategy under accident conditions	14
Editorial Board	14
Analysis on the influence of protection electrodes on the capacitance control rod position sensor	13
Editorial Board	13
A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay	13
Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation	13
A molecular-kinetic theory based model for alkali liquid metal boiling incipience analysis	13
Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids	13
Development of a practical control-oriented mathematical model for gas pressurizer	13
Oxidation and dissolution behavior of UZr alloys for aqueous reprocessing applications	13
Optimization of synthesis conditions for preparation of radiation grafted polymeric fibers and process variables of adsorption with response surface methodology	13
Investigation on aerosol removal by spray droplets under severe accident conditions	13
Gels, coatings and foams for radioactive surface decontamination: State of the art and challenges for the nuclear industry	13
Analysis of UO2, UN and U–10Zr fuels burning in a MegaPower reactor with solid monolithic and independent fuel element core designs	13
Security measurement of instrumentation systems: A case study of NPP	13
Equivalence method and transient flow characteristics of the integrated valve	13
Onset and evolution of counter-rotating baroclinic vortex pair in shock induced aerobreakup of droplets	13
Availability analysis of safety-critical systems of nuclear power plant using ordinary differential equations and reachability graph	13
A First collision source method using spherical harmonics method for arbitrary shape and order finite element mesh	13
An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow	12
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	12
Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties	12
Numerical simulation study on the filtration performance of metal fiber filters	12
Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE	12
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	12
Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor	12
Prediction and analysis of decay heat transfer in the core of the pebble bed reactor	12
Multi-step prediction of main pump leakage in nuclear power plants with an additive model	12
Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite	12
Detailed transient modeling and FPGA-based real-time digital-twin development for sodium-cooled fast reactor	12
Effect of H and Pd atoms on the migration of He atoms in 3C–SiC	12
Measurement of helium thermophysical properties and modification of the calculation models in the KTA 3102.1 report	12
Experimental study and numerical simulation on hydro-dynamic characteristics of cylindrical floating nuclear power platform	12
Review of melt-coolant interaction phenomenon in liquid metal cooled reactors: studies on low-temperature coolant impinging into high-temperature melt pool	12
Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling	12
Hydrogen risk analysis in small containment with a pressure suppression tank	12
Application of similarity analysis method in neutronics design of multi-purpose experimental reactor	12
LOFA and LOUHS analysis on the energy well SMR using TRACE code	11
Static performance of capacitance control rod position sensor: A review	11
Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture	11
A probabilistic model for the simulation of radioactivity transport through a heterogeneous porous medium	11
Causative process related method for the design of a reduced scale test facility for boron dispersion analysis in the pressurizer of SMRs	11
Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids	11
Investigation of radiation shielding properties of basalt-based glasses: Binodal/Spinodal decomposition effect theory	11
Experimental research on thermal-hydraulic characteristics of generation Ⅲ PWR under LOCA conditions	11
Performance comparison of the optimized k-section squared-off cascades for enrichment of 124Te using two meta-heuristic paradigms	11
Development of thermo-physical property database and code of fusion materials for CFETR blankets	11
Enhancing fuel breed-burn performance in a sodium-cooled fast reactor using a novel reactivity control method	11
Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel	11
Experiment investigation of a secondary PRHR cooling effect on an integral facility after a LOCA accident	11
Thermal-hydraulic analysis of PWR fuel assemblies based on the MSM	11
The technology of shielding design for nuclear reactor: A review	11
Flow distribution characteristics of parallel narrow rectangular channels under deformation conditions -Part I: An experimental study	11
Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel	11
Experimental and numerical analysis of sloshing in annular sectored containers under tangential direction excitation	11
Response function for optical fiber based gamma thermometer in data analytic methodology for OFBGT array	11
Research on fluctuation attenuation and optimization of passive residual heat removal system based on spring vibrator	11
Effect of strontium and cesium on corrosion and contamination of 316L stainless steels during spent nuclear fuel reprocessing	11
Characterization of plasma catalytic system degradation of low concentration 14CH4	11
Electrochemical decladding of used nuclear fuel	11
A losses and hazards identification process (LHIP) when connecting an additional system	11
A novel automated thickness measurement method and device for nuclear fuel plates	11
RHR water intake pipeline special hydraulic phenomenon test verification	11
Chemical states and reactions in multicomponent and multiphase systems containing different nuclide quantities	11
Research on internal flow characteristics of gas-liquid two-phase flow in reactor coolant pump	11
Review of researches on flow blockage accident in liquid-metal-cooled reactor	10
Study on flow heat transfer characteristics and mechanism of lithium-lead and helium-xenon	10
Synthesis and characterization of rare-earth doped aluminium phosphate glasses	10
Non-destructive evaluation and machine learning methods for inspection of spent nuclear fuel canisters: A state-of-the-art review	10
Development of a plug-and-play anti-noise module for fault diagnosis of rotating machines in nuclear power plants	10
A review on properties required for FB-CVD fabricated SiC for TRISO fuel production	10
Using advanced machine learning techniques to improve equipment health monitoring in NPPs	10
Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures	10
Experimental and numerical study of single bubble migration behavior in stagnant molten LBE	10
Evaluating the performance of passive second-stage hydro accumulators to enhance safety margins at Bushehr NPP	10
Supercritical carbon dioxide critical flow model based on deep learning	10
Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review	10