Progress in Nuclear Energy

Article	Citations
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	280
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	182
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	176
Editorial Board	141
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	107
Research on equipment survivability assessment in severe accidents for CANDU6	101
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct	100
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	95
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	93
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	92
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	85
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	80
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	79
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	74
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	73
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	73
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	69
Analysis schemes to evaluate HELB-induced blast waves	68
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	58
Detail CFD simulation of the integrated reactor pressure vessel of SMART	52
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	51
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	50
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	47
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	47
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	47

Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	47
Eigenvalues of the neutron transport equation in X–	41
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	40
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	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
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	38
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	37
Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors	37
Finding a suitable fuel type for the disposal of the accumulated minor actinides in the spent nuclear fuel in PWR	36
Numerical study on the interface debonding effect on FCM fuel behavior	36
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	36
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel	35
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	34
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	34
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	33
Status, opportunities, and challenges of nuclear power development in Sub-Saharan Africa: The case of Ghana	33
Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations	33
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	33
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	33
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	32
Static output feedbackH∞	32
Evaluating the impact of airborne radionuclides caused by the Fukushima nuclear accident on China based on global atmospheric dispersion	32
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	32
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	31
Experimental study on polydisperse aerosol removal under multi-parameter spray conditions in containment	31
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	31
Scaling deep learning for whole-core reactor simulation	30
Editorial Board	30
Effects of elevated temperature steam oxidation and subsequent quenching on light water reactor clad	30
Developing a robust and flexible smart tool to predict a full range Critical Heat Flux (CHF) in different LWRs by using deep learning Artificial Neural Networks (ANN) via parallel multi-processing	30
Thermo-neutronic integrated coupling effects on nuclear reactor core calculations	30
Radiological characterization plan for decommissioning IFIN-HH's Cyclotron	30
Effect of smectite illitization on swelling behavior of Gyeongju bentonite	29
Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison	29
A world's dilemma ‘upon which the sun never sets’: The nuclear waste management strategy (part III): Australia, Belgium, Czech Republic, Netherlands, and Romania	29
Quantitative analysis of contributing factors to the resilience of emergency response organizations in nuclear power plants	28
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	28
A detailed design for a radioactive waste safety management system using ICT technologies	28
Availability assessment of a nuclear reactor limitation system by a Timed Petri Net	27
Experimental study of three-dimensional trajectory and dynamic characteristics of rising bubbles	27
Experimental and theoretical investigation on the effect of surface porosity on the nucleate flow boiling heat transfer	27
Study on bubble growth interphase heat transfer of rapid decompression	27
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	26
Visual experimental study on bubble characteristics near the heating wall in subcooled flow boiling	26
Investigation of the pulsed neutron source method measuring the fission decay properties of a subcritical assembly with low-Z reflectors	25
Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies	25
Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface	25
Dissolved ozone coupled permanganate based process for chemical decontamination of stainless steel surfaces	25
Atlas of historical and proposed nuclear devices and power systems in the Earth-Moon System and wider Solar System	24
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization	24

Radiation shielding properties of flexible liquid metal-GaIn alloy	24
Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs	24
Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications	23
Sensitivity and uncertainty analysis of neutron activation source terms based on statistical sampling method	23
Revealing the nexus between nuclear energy and ecological footprint in STIRPAT model of advanced economies: Fresh evidence from novel CS-ARDL model	22
Experimental estimates of hygroscopic growth of particulate fission product species (mixed CsI–CsOH) with implications in reactor accident safety research	22
Advances in technology, design and deployment of microreactors- a review	22
Fragility analysis of nuclear containment under inner pressure based on a simplified method and program (NCMC)	22
Thermal air oxidation of UO2: Joint effect of precursor's nature and particle size distribution	22
The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks: An experimental study	22
Separation anion and cation exchange resins using fluidization and adjusted NaOH solution density methods	22
Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems	21
Reliability Analysis of Safety-Critical Systems using Optimized Petri Nets	21
Numerical research on the influence of inlet shape on the air flow and heat transfer characteristics inside the reactor channel	21
Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics	20
The time for revolutionizing small modular reactors: Cost reduction strategies from innovations in operation and maintenance	20
Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test	20
Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR	20
Development of a membrane reactor with a closed-end silica membrane for nuclear-heated hydrogen production	20
Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces	20
Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel	20
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	20
Unsupervised anomaly detection for Nuclear Power Plants based on Denoising Diffusion Probabilistic Models	19
Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels	19
Research on the radioactive safety of industrial steam supplied by PWR nuclear power plant	19
Enhancing the radiation shielding performance of polyepoxide composites based on cement bypass dust	19
Meso-scale numerical analysis for transport and deposition behaviors of radioactive aerosols under severe nuclear accident	19
Thermal-hydraulic performance of natural circulation system with narrow rectangular channel under heaving condition based on 1D/3D coupling analysis	19
Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations	19
CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system	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
Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident	18
Survey of cyber risk analysis techniques for use in the nuclear industry	18
Experimental analysis of forced convection heat transfer of Hybrid Nanofluids in a vertical annulus with cosine heat flux	18
The development of high temperature heat-pipe transient model for system analysis of heat pipe cooled microreactor	18
Low-temperature heat capacities for EMoO4 (E=Mg, Sr, Ba) substances formed in nuclear fuel waste glasses	18
Neighboring country's nuclear power plant? “No, thanks”: An energy justice analysis	18
Measuring void fraction in vertical air–water bubbly flow using echo intensity and visualization techniques	18
Development of fuel depletion code for molten salt reactor with very deep burnup	17
Nonlinear vibrations analysis of a fuel rod in nuclear heating reactor	17
Design of fractional-order NPID controller for the NPK model of advanced nuclear reactor	17
Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications	17
A state-aware adaptive pathfinder for dynamic minimum dose path planning during an emergency in a complex radioactive environment	17
SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model	17
Transient fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics method	17
CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle	17
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	17
Influence of the concentration of nitric acid on the composition of NOX gas evolved during the dissolution of nuclear fuel and its implications on the PUREX process	17
Neutron sensitivity and uncertainty analysis of rhodium self-powered neutron detectors for reactor monitoring in HPR1000	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
Analysis on waterproofing design in CCS pump building of PWR under main feed water pipe broken accident	16
A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions	16
Uncertainty analysis of HPR-1000 LOCA with probabilistic and deterministic methods	16
Editorial Board	16
Numerical study of hydraulic fragmentation of melt jet in coolant: Breakup length and melt-coolant contact area	15
CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel	15
Numerical and experimental study on natural convection outside tube bundle under small convection temperature difference	15
Lithium isotopic analysis in depleted lithium salts	15
Pilot study of response-order effects on survey on young Chinese's perceptions of nuclear power	15
Modeling a three-layer container based on halloysite nano-clay for radioactive waste disposal	15
Development and integration of a tool for physics-based shape and topology optimization in the MOOSE multiphysics simulation framework	15
Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh	15
3-D gamma dose rate reconstruction for a radioactive waste processing facility using sparse and arbitrarily-positioned measurements	15
Investigation of optical, mechanical, and shielding properties of zirconia glass capsule	15
Preliminary neutronics optimization on the concept of multi-beam accelerator driven system	15
A Newton-Krylov method with dense row decomposition for steady-state neutronics/thermal-hydraulics problems	15
Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC	14
Numerical approximation of a fractional neutron diffusion equation for neutron flux profile in a nuclear reactor	14
An attempt to find the optimal loading pattern of minor actinides in the PWR fuel rods	14
Radiometric techniques for the detection and assessment of tritium in aqueous media - a review	14
Large leakage sodium-water reaction accident analysis in a sodium-cooled fast reactor with paralleling steam generators	14
Effect of H and Pd atoms on the migration of He atoms in 3C–SiC	14
Verification of the NACAC atmospheric dispersion calculation using a hypothetical accident in a neighboring nuclear power plant	14
Experimental research on the two-phase turbulent mixing between rod bundle subchannels with spacer grid	14
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign	14
Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX	14
CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties	14
Optimization of synthesis conditions for preparation of radiation grafted polymeric fibers and process variables of adsorption with response surface methodology	14
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	14

Numerical simulation study of liquid sodium contact angle on gradient sodium-philic nanostructure surface based on Lattice Boltzmann method for heat pipe rector application	14
Simulation model for investigating safety margin of three-layer molten pool after late phase in-vessel water injection	14
Irradiation in BCC materials: Defect-induced changes of the effective dislocation mobility and their relation with the dose-dependent fracture response	14
Hybrid IACO-A*-PSO optimization algorithm for solving multiobjective path planning problem of mobile robot in radioactive environment	14
Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites	14
Investigating the effects of natural gas, nuclear energy, and democracy on environmental footprint and energy risk in France: Does financial inclusion matter?	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	13
Analysis on the influence of protection electrodes on the capacitance control rod position sensor	13
Hydrogen risk analysis in small containment with a pressure suppression tank	13
Security measurement of instrumentation systems: A case study of NPP	13
Analysis of unprotected loss of flow accident in a sodium cooled fast reactor using coupled thermal hydraulics neutronics code ASTRA	13
Numerical simulation study on the filtration performance of metal fiber filters	13
A First collision source method using spherical harmonics method for arbitrary shape and order finite element mesh	13
Availability analysis of safety-critical systems of nuclear power plant using ordinary differential equations and reachability graph	13
A molecular-kinetic theory based model for alkali liquid metal boiling incipience analysis	13
Editorial Board	13
A proposed improvement for the design of safety injection system in VVER-1000/V446 reactor	13
Editorial Board	13
Oxidation and dissolution behavior of UZr alloys for aqueous reprocessing applications	13
Onset and evolution of counter-rotating baroclinic vortex pair in shock induced aerobreakup of droplets	13
Evaluation of management measures on a hypothetical accident in Unit-1 of bushehr nuclear power plant	13
Development of a practical control-oriented mathematical model for gas pressurizer	13
Equivalence method and transient flow characteristics of the integrated valve	13
Moisture-carryover performance optimization using physics-constrained machine learning	12
Investigation on aerosol removal by spray droplets under severe accident conditions	12
Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies	12
Gels, coatings and foams for radioactive surface decontamination: State of the art and challenges for the nuclear industry	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
Prediction and analysis of decay heat transfer in the core of the pebble bed reactor	12
A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay	12
Measurement of helium thermophysical properties and modification of the calculation models in the KTA 3102.1 report	12
Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation	12
Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor	12
Linked calculation method based on next event estimation for directional shielding problems	12
Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids	12
Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks	12
Application of similarity analysis method in neutronics design of multi-purpose experimental reactor	12
Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling	12
Analysis of UO2, UN and U–10Zr fuels burning in a MegaPower reactor with solid monolithic and independent fuel element core designs	12
Multi-step prediction of main pump leakage in nuclear power plants with an additive model	12
Applicability of polymer and composite inner linings in containers for borehole disposal of sealed radioactive sources − A simulation-based study of radiation effects	12
An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow	12
Experiment investigation of a secondary PRHR cooling effect on an integral facility after a LOCA accident	11
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	11
Experimental study on convective heat transfer of S–CO2 under high heat flux	11
Investigation of radiation shielding properties of basalt-based glasses: Binodal/Spinodal decomposition effect theory	11
Design and simulation of neutron radiography system for an aqueous homogeneous solution reactor	11
Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE	11
Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures	11
A losses and hazards identification process (LHIP) when connecting an additional system	11
A framework to implement human reliability analysis during early design stages of advanced reactors	11
Wireless coupling for LVDT sensor for reactor applications	11
The technology of shielding design for nuclear reactor: A review	11
Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties	11
Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite	11
Causative process related method for the design of a reduced scale test facility for boron dispersion analysis in the pressurizer of SMRs	11
Flow distribution characteristics of parallel narrow rectangular channels under deformation conditions -Part I: An experimental study	11
A probabilistic model for the simulation of radioactivity transport through a heterogeneous porous medium	11
Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture	11
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	11
Numerical modelling of catalytic hydrogen combustion in passive autocatalytic recombiners: A review	11
Static performance of capacitance control rod position sensor: A review	11
Thermal-hydraulic analysis of PWR fuel assemblies based on the MSM	10
Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel	10
Performance comparison of the optimized k-section squared-off cascades for enrichment of 124Te using two meta-heuristic paradigms	10
An accessible statistical regression approach for the estimation of spent nuclear fuel compositions and decay heats to support the development of nuclear fuel management strategies	10
Electrochemical decladding of used nuclear fuel	10
Response function for optical fiber based gamma thermometer in data analytic methodology for OFBGT array	10
The Lagrangian particle-based simulation of finned freeze plugs melting in the molten salt reactor	10
Can BRICS economies shift some burden on nuclear energy efficiency for sustainable environment? An empirical investigation	10
Preparation and properties of visible light-cured strippable film for radioactive decontamination	10
Numerical simulation of flow field and metal deposition of Joule-heated ceramic melter for vitrification of radioactive waste	10
Research on fluctuation attenuation and optimization of passive residual heat removal system based on spring vibrator	10
Synthesis and characterization of rare-earth doped aluminium phosphate glasses	10
Mixed-oxide fuel strategies in an integral pressurized water reactor	10
Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids	10
A novel automated thickness measurement method and device for nuclear fuel plates	10
RHR water intake pipeline special hydraulic phenomenon test verification	10
Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review	10
Enhancing fuel breed-burn performance in a sodium-cooled fast reactor using a novel reactivity control method	10
LOFA and LOUHS analysis on the energy well SMR using TRACE code	10
Effect of strontium and cesium on corrosion and contamination of 316L stainless steels during spent nuclear fuel reprocessing	10
Impact of adding high-concentration neutron poisons to reactor moderator system for guaranteed shutdown	9
FPGA-based real-time implementation of a digital reactivity-meter	9
Data and modeling sensitivity analysis for molten salt fast reactor benchmark – Static calculations	9
Design and optimization of three segmented thermoelectric generator for nuclear reactor application	9
The operational assessment of steam generator tubes based on a stochastic crack growth model	9
Dissolution of chromium containing oxides by dissolved ozone (DOz) coupled with permanganate: A novel method to decontaminate radioactive surfaces of nuclear facilities	9
Research on backflow characteristics in U-tube of forced circulation steam generator under ocean conditions	9
Development of advanced AI-based segmentation and prediction method for air entrainment in plunging water jets	9
Evaluation of the relative deviation for coagulation and gravitational sedimentation model from experimental results of submicron aerosol in water vapor environments	9
Extended development of the Monte Carlo code MCNP for effective delayed neutron fraction calculation in molten salt reactors	9
IMUPF-BIN: A new autonomous search method for radioactive sources	9
Development and validation of the helically coiled steam generator model of RELAP5/MOD3.4 code	9
Relaxation effects in nuclear fuel coupled calculations using serpent-OpenFOAM codes	9