Progress in Nuclear Energy

Article	Citations
Editorial Board	291
Research on equipment survivability assessment in severe accidents for CANDU6	212
Influence of throat and diverging section on the performance of venturi scrubber by using computational fluid dynamics	186
Study on transient characteristics for bypass valve regulation and load rejection of microreactor with helium Brayton cycle	147
Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method	128
A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior	113
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review	108
Numerical study of forced circulation and natural circulation transition characteristics of a small modular reactor equipped with helical-coiled steam generators	102
Post-irradiation examination of silicide fuel (U3Si2-Al) with 4.8 gU/cm3 for RSG-GAS	100
Development of a numerical model for disassembly phase of hypothetical core disruptive accident and application to a medium-sized mixed oxide fuelled fast reactor	99
Study of fluid-elastic instability of the spatially bent tube structure in fast reactor intermediate heat exchanger	89
Analysis schemes to evaluate HELB-induced blast waves	84
Detail CFD simulation of the integrated reactor pressure vessel of SMART	80
Theoretical study on pressure oscillation dominant frequency of bubbles submerged jet under rolling condition	76
Weierstrass function methodology for uncertainty analysis of random media criticality with spectrum range control	73
A comparison study on the burnup of HTR-10 fuels using radiometric and mass spectrometric methods	72
Improvement on Fourier fundamental mode coefficient for Monte Carlo criticality calculations	68
Neutron and gamma radiation effects on thermal storage properties of polyethylene wax	56
Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement	54
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects	53
Static output feedbackH∞	51
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor	50
Evaluating the impact of airborne radionuclides caused by the Fukushima nuclear accident on China based on global atmospheric dispersion	45
Numerical study on the interface debonding effect on FCM fuel behavior	44
Physics-Informed Neural Networks for the safety analysis of nuclear reactors	43

Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb	43
Eigenvalues of the neutron transport equation in X–	42
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	39
An evaluation of techniques for the measurement of fission gas in irradiated fuel rods	39
CFD simulation on sub-channel blockage in the fuel plate of RSG-GAS reactor	39
Self-sustainability and energy-balance in a fast Fusion–Fission Hybrid Reactor (FFHR) based on Dense Plasma Focus (DPF) and multiplicative cascade	39
Assessment of thermal shock resistance of refractory magnesia lining under simulated core melt impingement for application to SFR core catcher	38
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	38
Research and development of the neutron-photon coupled transport method in the fast reactor code system MOSASAUR	38
Status, opportunities, and challenges of nuclear power development in Sub-Saharan Africa: The case of Ghana	37
Bus based emergency evacuation organization strategy of nuclear power plant planning restricted area	36
Primary study on the recovery of lead from waste flexible X/Gamma ray shielding materials using pyrolysis	36
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor	36
Potential flame retardancy of high-density polyethylene (HDPE) composite for possible use as a radiation shield	35
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	35
U(VI) speciation studies by Raman spectroscopy technique in the production of nuclear fuel	34
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results	34
Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors	34
Performance analysis of indirect contact heat pipe radiator for space nuclear power system	34
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data	34
Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors	34
Radiological characterization plan for decommissioning IFIN-HH's Cyclotron	33
Comprehensive analysis of the effects of Mo and Co on the synthesis, structural, and radiation-shielding properties of TiO2 based composites	33
Editorial Board	33
Fault diagnosis in reactor coolant pump with an automatic CNN-based mixed model	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
Experimental and theoretical investigation on the effect of surface porosity on the nucleate flow boiling heat transfer	32
Visual experimental study on bubble characteristics near the heating wall in subcooled flow boiling	32
Availability assessment of a nuclear reactor limitation system by a Timed Petri Net	32
Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies	30
Investigation of the pulsed neutron source method measuring the fission decay properties of a subcritical assembly with low-Z reflectors	29
Assessment of RELAP5/SCDAPSIM code against NACIE-UP facility tests	29
Numerical research on the influence of inlet shape on the air flow and heat transfer characteristics inside the reactor channel	28
Thermo-neutronic integrated coupling effects on nuclear reactor core calculations	28
Study on bubble growth interphase heat transfer of rapid decompression	28
Thermal-hydraulic performance of natural circulation system with narrow rectangular channel under heaving condition based on 1D/3D coupling analysis	28
Prediction of core unmeasurable parameters during loss of coolant accident using deep neural network method	28
Experimental estimates of hygroscopic growth of particulate fission product species (mixed CsI–CsOH) with implications in reactor accident safety research	27
Enhancing the radiation shielding performance of polyepoxide composites based on cement bypass dust	27
Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface	27
METAL: Methodology for liquid metal fast reactor core economic design and fuel loading pattern optimization	27
Separation anion and cation exchange resins using fluidization and adjusted NaOH solution density methods	26
A detailed design for a radioactive waste safety management system using ICT technologies	26
Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems	25
Advanced and Small Modular Reactors’ supply chain: Current status and potential for global cooperation	25
Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel	25
Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR	25
Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces	24
Scaling deep learning for whole-core reactor simulation	24
Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs	24

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
Sensitivity and uncertainty analysis of neutron activation source terms based on statistical sampling method	23
Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics	23
Effects of elevated temperature steam oxidation and subsequent quenching on light water reactor clad	23
Quantitative analysis of contributing factors to the resilience of emergency response organizations in nuclear power plants	22
Experimental study on polydisperse aerosol removal under multi-parameter spray conditions in containment	22
A world's dilemma ‘upon which the sun never sets’: The nuclear waste management strategy (part III): Australia, Belgium, Czech Republic, Netherlands, and Romania	22
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	22
Thermal air oxidation of UO2: Joint effect of precursor's nature and particle size distribution	22
Atlas of historical and proposed nuclear devices and power systems in the Earth-Moon System and wider Solar System	22
Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison	21
The time for revolutionizing small modular reactors: Cost reduction strategies from innovations in operation and maintenance	21
Advances in technology, design and deployment of microreactors- a review	20
The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks: An experimental study	20
Fragility analysis of nuclear containment under inner pressure based on a simplified method and program (NCMC)	20
Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications	20
Revealing the nexus between nuclear energy and ecological footprint in STIRPAT model of advanced economies: Fresh evidence from novel CS-ARDL model	20
Experimental study of three-dimensional trajectory and dynamic characteristics of rising bubbles	20
Effect of smectite illitization on swelling behavior of Gyeongju bentonite	20
Reliability Analysis of Safety-Critical Systems using Optimized Petri Nets	20
Research on the radioactive safety of industrial steam supplied by PWR nuclear power plant	20
Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test	20
Unsupervised anomaly detection for Nuclear Power Plants based on Denoising Diffusion Probabilistic Models	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
Preliminary neutronics optimization on the concept of multi-beam accelerator driven system	19
Experimental research on the two-phase turbulent mixing between rod bundle subchannels with spacer grid	19
Advancements to generalized equivalence theory for preserving cross-sections of whole core simulations	19
Numerical simulation study of liquid sodium contact angle on gradient sodium-philic nanostructure surface based on Lattice Boltzmann method for heat pipe rector application	19
Experimental study on startup performance of sodium heat pipe with high ratio of length-to-diameter under different coolant flow rates	19
Meso-scale numerical analysis for transport and deposition behaviors of radioactive aerosols under severe nuclear accident	19
3-D gamma dose rate reconstruction for a radioactive waste processing facility using sparse and arbitrarily-positioned measurements	19
Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries	18
A Newton-Krylov method with dense row decomposition for steady-state neutronics/thermal-hydraulics problems	18
Experimental analysis of forced convection heat transfer of Hybrid Nanofluids in a vertical annulus with cosine heat flux	18
Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident	18
Neighboring country's nuclear power plant? “No, thanks”: An energy justice analysis	18
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	18
Transient fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics method	18
Survey of cyber risk analysis techniques for use in the nuclear industry	18
Numerical and experimental study on natural convection outside tube bundle under small convection temperature difference	18
Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh	17
A state-aware adaptive pathfinder for dynamic minimum dose path planning during an emergency in a complex radioactive environment	17
Editorial Board	17
Pilot study of response-order effects on survey on young Chinese's perceptions of nuclear power	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
Numerical study of hydraulic fragmentation of melt jet in coolant: Breakup length and melt-coolant contact area	17
A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions	17
CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system	17
Development and integration of a tool for physics-based shape and topology optimization in the MOOSE multiphysics simulation framework	17
Preliminary validation of the 1D modeling of the DYNASTY natural circulation loop against results from water experimental campaign	17
Radiometric techniques for the detection and assessment of tritium in aqueous media - a review	17
Analysis on waterproofing design in CCS pump building of PWR under main feed water pipe broken accident	17
Assessment of neutronics performance of U3Si, U3Si2, and U–9Mo fuels for the support of MNSR conversion using SCALE 6.2.3 computational tools	17
Lithium isotopic analysis in depleted lithium salts	17
Verification of the NACAC atmospheric dispersion calculation using a hypothetical accident in a neighboring nuclear power plant	17
CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel	17
Design of fractional-order NPID controller for the NPK model of advanced nuclear reactor	16
The development of high temperature heat-pipe transient model for system analysis of heat pipe cooled microreactor	16
Low-temperature heat capacities for EMoO4 (E=Mg, Sr, Ba) substances formed in nuclear fuel waste glasses	16
Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites	16
CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties	16
Transient characteristics of supercritical carbon dioxide Brayton cycle system with or without control strategy under accident conditions	16
Large leakage sodium-water reaction accident analysis in a sodium-cooled fast reactor with paralleling steam generators	16
Assessment of interfacial area model for two-phase flows in rod bundles implemented in RELAP5 code	16
Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC	16
Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications	16
Investigation of flow-induced vibration in core sub-assemblies of sodium-cooled fast reactors	16
Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels	16
Irradiation in BCC materials: Defect-induced changes of the effective dislocation mobility and their relation with the dose-dependent fracture response	15
Hybrid IACO-A*-PSO optimization algorithm for solving multiobjective path planning problem of mobile robot in radioactive environment	15
Simulation model for investigating safety margin of three-layer molten pool after late phase in-vessel water injection	15
Nonlinear vibrations analysis of a fuel rod in nuclear heating reactor	15
Neutron sensitivity and uncertainty analysis of rhodium self-powered neutron detectors for reactor monitoring in HPR1000	15
Uncertainty analysis of HPR-1000 LOCA with probabilistic and deterministic methods	15
SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model	15
Numerical approximation of a fractional neutron diffusion equation for neutron flux profile in a nuclear reactor	15
Development of fuel depletion code for molten salt reactor with very deep burnup	15
An attempt to find the optimal loading pattern of minor actinides in the PWR fuel rods	15
Analysis on the influence of protection electrodes on the capacitance control rod position sensor	14
Security measurement of instrumentation systems: A case study of NPP	14

Measurement of helium thermophysical properties and modification of the calculation models in the KTA 3102.1 report	14
Editorial Board	14
Editorial Board	14
Investigating the effects of natural gas, nuclear energy, and democracy on environmental footprint and energy risk in France: Does financial inclusion matter?	14
Onset and evolution of counter-rotating baroclinic vortex pair in shock induced aerobreakup of droplets	14
Development of a practical control-oriented mathematical model for gas pressurizer	14
Equivalence method and transient flow characteristics of the integrated valve	14
Numerical simulation study of boiling Critical Heat Flux characteristics of graphene nanofluids	14
Interfacial behaviors, kinetic analysis and dynamic parameters of disturbance waves in 3 × 3 rod bundle channels	14
CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle	14
Investigation of optical, mechanical, and shielding properties of zirconia glass capsule	14
A First collision source method using spherical harmonics method for arbitrary shape and order finite element mesh	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
Prediction and analysis of decay heat transfer in the core of the pebble bed reactor	14
Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX	14
Modeling a three-layer container based on halloysite nano-clay for radioactive waste disposal	14
A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay	13
Optimization of synthesis conditions for preparation of radiation grafted polymeric fibers and process variables of adsorption with response surface methodology	13
Oxidation and dissolution behavior of UZr alloys for aqueous reprocessing applications	13
Linked calculation method based on next event estimation for directional shielding problems	13
Investigation on aerosol removal by spray droplets under severe accident conditions	13
Analysis of unprotected loss of flow accident in a sodium cooled fast reactor using coupled thermal hydraulics neutronics code ASTRA	13
Review of melt-coolant interaction phenomenon in liquid metal cooled reactors: studies on low-temperature coolant impinging into high-temperature melt pool	13
Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE	13
Numerical modelling of catalytic hydrogen combustion in passive autocatalytic recombiners: A review	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
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	13
Availability analysis of safety-critical systems of nuclear power plant using ordinary differential equations and reachability graph	13
Design and simulation of neutron radiography system for an aqueous homogeneous solution reactor	13
Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling	13
Analysis of UO2, UN and U–10Zr fuels burning in a MegaPower reactor with solid monolithic and independent fuel element core designs	13
Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation	13
Application of similarity analysis method in neutronics design of multi-purpose experimental reactor	13
Multi-step prediction of main pump leakage in nuclear power plants with an additive model	13
Hydrogen risk analysis in small containment with a pressure suppression tank	12
The technology of shielding design for nuclear reactor: A review	12
Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor	12
Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties	12
Causative process related method for the design of a reduced scale test facility for boron dispersion analysis in the pressurizer of SMRs	12
Numerical simulation study on the filtration performance of metal fiber filters	12
Gels, coatings and foams for radioactive surface decontamination: State of the art and challenges for the nuclear industry	12
Transient characteristics and adjustment ranges of key parameters in supercritical CO2 direct-cooled microreactor system with simplified control strategies	12
Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks	12
Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture	12
Experiment investigation of a secondary PRHR cooling effect on an integral facility after a LOCA accident	12
An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow	12
Effect of H and Pd atoms on the migration of He atoms in 3C–SiC	12
Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite	12
A molecular-kinetic theory based model for alkali liquid metal boiling incipience analysis	12
Static performance of capacitance control rod position sensor: A review	12
Investigation of radiation shielding properties of basalt-based glasses: Binodal/Spinodal decomposition effect theory	12
Core design and fuel behaviour of a small modular pressurised water reactor using (Th,U)O	11
Wireless coupling for LVDT sensor for reactor applications	11
Thermal-hydraulic analysis of PWR fuel assemblies based on the MSM	11
Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review	11
Development of a plug-and-play anti-noise module for fault diagnosis of rotating machines in nuclear power plants	11
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	11
Response function for optical fiber based gamma thermometer in data analytic methodology for OFBGT array	11
Investigation of hybrid nanofluids effects on heat transfer characteristics in VVER-1000 nuclear reactor	11
Experimental study on convective heat transfer of S–CO2 under high heat flux	11
Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids	11
Can BRICS economies shift some burden on nuclear energy efficiency for sustainable environment? An empirical investigation	11
Performance comparison of the optimized k-section squared-off cascades for enrichment of 124Te using two meta-heuristic paradigms	11
A novel automated thickness measurement method and device for nuclear fuel plates	11
A review of VOF methods for simulating bubble dynamics	11
LOFA and LOUHS analysis on the energy well SMR using TRACE code	11
Effect of strontium and cesium on corrosion and contamination of 316L stainless steels during spent nuclear fuel reprocessing	11
Role of Sm3+ ions as network-modifying on elastic, mechanical, and radiation shielding properties of MgO–B2O3–TeO2 glasses	11
Flow distribution characteristics of parallel narrow rectangular channels under deformation conditions -Part I: An experimental study	11
RHR water intake pipeline special hydraulic phenomenon test verification	11
A probabilistic model for the simulation of radioactivity transport through a heterogeneous porous medium	11
How does nuclear energy consumption contribute to or hinder green growth in major nuclear energy-consuming countries?	11
A framework to implement human reliability analysis during early design stages of advanced reactors	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
The role of nuclear energy in the carbon neutrality goal	11
Data and modeling sensitivity analysis for molten salt fast reactor benchmark – Static calculations	10
Supercritical carbon dioxide critical flow model based on deep learning	10
Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel	10
Non-destructive evaluation and machine learning methods for inspection of spent nuclear fuel canisters: A state-of-the-art review	10
Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures	10
Preparation and properties of visible light-cured strippable film for radioactive decontamination	10
Research on backflow characteristics in U-tube of forced circulation steam generator under ocean conditions	10
Development of advanced AI-based segmentation and prediction method for air entrainment in plunging water jets	10
Review of researches on flow blockage accident in liquid-metal-cooled reactor	10
A losses and hazards identification process (LHIP) when connecting an additional system	10
Refinement of optical/structural features and neutron/gamma-ray protecting capability of P2O5–Li2O–BaO phosphate glass system by adding Bi2O3	10
A review on properties required for FB-CVD fabricated SiC for TRISO fuel production	10
Designing a molten core collection chamber for Bushehr-1 nuclear power plant using MELCOR 1.8.6 and ANSYS-FLUENT codes	10
Development and validation of the helically coiled steam generator model of RELAP5/MOD3.4 code	10
Impact of adding high-concentration neutron poisons to reactor moderator system for guaranteed shutdown	10
Mixed-oxide fuel strategies in an integral pressurized water reactor	10
Synthesis and characterization of rare-earth doped aluminium phosphate glasses	10
Evaluating the performance of passive second-stage hydro accumulators to enhance safety margins at Bushehr NPP	10
Electrochemical decladding of used nuclear fuel	10
Dissolution of chromium containing oxides by dissolved ozone (DOz) coupled with permanganate: A novel method to decontaminate radioactive surfaces of nuclear facilities	10