Nuclear Engineering and Technology

Papers
(The median citation count of Nuclear Engineering and Technology is 2. 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
Beyond design basis seismic evaluation of underground liquid storage tanks in existing nuclear power plants using simple method198
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations180
Nuclear power utilization as a future alternative energy on icebreakers142
Investigation on the thermal characteristics of electronic system and prediction of chip temperature by machine learning110
A study on the applicability of simplified few-group GET (Generalized Equivalence Theory) to cylindrical molten salt fast reactor94
Fission accelerated steady-state post irradiation examinations - Part II90
COFUN: A new tool for evaluating containment failure frequency and uncertainty89
Influence of dissolved hydrogen and IG Cr carbide on the oxidation behavior of Alloy 600 in hydrogenated primary water79
CFD analysis of the flow blockage in a rectangular fuel assembly of the IAEA 10 MW MTR research reactor63
Thermal-hydraulic phenomena and heat removal performance of a passive containment cooling system according to exit loss coefficient61
Fabrication, characterization, simulation and experimental studies of the ordinary concrete reinforced with micro and nano lead oxide particles against gamma radiation58
Pump availability prediction using response surface method in nuclear plant56
Photon dose response functions for accurate skeletal dosimetry for Korean and Asian populations55
Investigation of neural network-based cathode potential monitoring to support nuclear safeguards of electrorefining in pyroprocessing55
Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects51
Numerical investigation of two-component single-phase natural convection and thermal stratification phenomena in a rod bundle with axial heat flux profile49
Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods48
Differentiated influences of perceived benefit types of nuclear power on its acceptance: Evidence from South Korea46
Coupled heat and mass transfer simulation of CRUD migration and deposition in PWR systems44
Analysis of Naturally Occurring Radioactive Material (NORM) in shifting earth layers in Piyungan, Bantul44
Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning43
Graded approach to determine the frequency and difficulty of safety culture attributes: The F-D matrix42
Design and optimization of thermal neutron activation device based on 5 MeV electron linear accelerator40
Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor40
Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code39
SEM-based study on the impact of safety culture on unsafe behaviors in Chinese nuclear power plants39
Radioisotope identification using sparse representation with dictionary learning approach for an environmental radiation monitoring system39
Radioactive waste sampling for characterisation - A Bayesian upgrade38
Validation of the correlation-based aerosol model in the ISFRA sodium-cooled fast reactor safety analysis code37
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code37
Discrimination of dicentric chromosome from radiation exposure patient data using a pretrained deep learning model36
Investigation of thorium separation from rare-earth extraction residue via electrosorption with carbon based electrode toward reducing waste volume35
Experimental evaluation of fatigue strength for small diameter socket welded joints under vibration loading condition35
Assessment of neutron-induced activation of irradiated samples in a research reactor35
Feasibility study of using triple-energy CT images for improving stopping power estimation33
Investigation of condensation with non-condensable gas in natural circulation loop for passive safety system32
Topology optimization of tie-down structure for transportation of metal cask containing spent nuclear fuel32
“Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography”31
Effects of decay heat and cooling condition on the reactor pool natural circulation under RVACS operation in a water 2-D slab model31
Anode processes on Pt and ceramic anodes in chloride and oxide-chloride melts30
Efficient elastic stress analysis method for piping system with wall-thinning and reinforcement30
Melting and draining tests on glass waste form for the immobilization of Cs, Sr, and rare-earth nuclides using a cold-crucible induction melting system30
Seismic demand estimation of electrical cabinet in nuclear power plant considering equipment-anchor-interaction29
Design of digital nuclear power small reactor once-through steam generator control system29
Performance prediction of gamma electron vertex imaging (GEVI) system for interfractional range shift detection in spot scanning proton therapy28
Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions28
On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation28
Water film covering characteristic on horizontal fuel rod under impinging cooling condition27
A hybrid approach of partially applying BDD for seismic PSA quantification27
Energy build-up factors estimation for BaZr0.10Ti0.90O3, Ba0.90La0.10TiO3 and Ba0.90La0.10Zr0.10Ti0.90O3 ceramics in shielding applications27
Corrosion behaviors of SS316L, Ti-Gr.2, Alloy 22 and Cu in KURT groundwater solutions for geological deep disposal27
Development of a dose estimation code for BNCT with GPU accelerated Monte Carlo and collapsed cone Convolution method27
A time-reliability correlation for estimating the diagnosis error probability of a nuclear power plant with up-to-date Human–Machine interfaces26
Numerical simulation on in-vessel molten corium behavior with external vessel cooling using smoothed particle hydrodynamics26
The effect of methyl yellow concentrations on the optical properties of polyvinyl chloride-methyl yellow film as a radiation dosimeter26
Development and validation of wall and interfacial friction models in LOCUST for reactor downcomer with direct vessel injection26
A comparison study between the realistic random modeling and simplified porous medium for gamma-gamma well-logging25
Thermal-hydraulic modeling of CAREM-25 advanced small modular reactor using the porous media approach and COBRA-EN modified code25
Analysis of signal cable noise currents in nuclear reactors under high neutron flux irradiation24
Hyphae and organic acids of Aspergillus Niger promote uranium recovery by destroying the ore surface and increasing the porosity and permeability of ores24
Determine the hazards of radioactive elements and radon gas manufacturing processes in an Egyptian fertilizer factory24
A counting-time optimization method for artificial neural network (ANN) based gamma-ray spectroscopy23
Experimental investigation on flow field around a flapping plate with single degree of freedom23
Balancing the nuclear equation: Climate policy uncertainty and budgetary dynamics22
Thermo-hydrodynamic investigation into the effects of minichannel configuration on the thermal performance of subcooled flow boiling22
Experimental setup for elemental analysis using prompt gamma rays at research reactor IBR-222
SSC risk significance in risk-informed, performance-based licensing of non-LWRs21
Investigation of gamma radiation shielding properties of polyethylene glycol in the energy range from 8.67 to 23.19 keV21
Assessment of CATHARE code against DEC-A upper head SBLOCA experiments21
Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes21
Hybrid of the fuzzy logic controller with the harmony search algorithm to PWR in-core fuel management optimization21
Preliminary study for the development of radiation safety evaluation methodology for industrial kV-rated radiation generator facilities20
The effect of sensitive and non-sensitive parameters on DCGL in probability analysis for decommissioning of nuclear facilities20
Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants20
Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neut20
Structural and radiological characterization of irradiated RBMK-1500 reactor graphite20
Study on the digitalization of trip equations including dynamic compensators for the Reactor Protection System in NPPs by using the FPGA20
A simple data assimilation method to improve atmospheric dispersion based on Lagrangian puff model19
Measurement of the ICRH antenna phasing using antenna strap probe based diagnostic system in EAST tokamak19
Influence of Ca–Na–Cl physicochemical solution properties on the adsorption of Se(-II) onto granite and MX-80 bentonite19
Utilization of EPRI ChemWorks tools for PWR shutdown chemistry evolution modeling19
Implementation of dynamic start-up test experimental data as a main part of the nuclear code validation procedure: Developed RELAP5 model for VVER-100019
Understanding the creep behavior of bentonite-sand mixtures as buffer materials in a low-level radioactive waste repository in Taiwan19
Role of modifiers on the structural, mechanical, optical and radiation protection attributes of Eu3+ incorporated multi constituent glasses19
Image reconstruction method of gamma emission tomography based on prior-aware information and machine learning for partial-defect detection of PWR-type spent nuclear fuel19
Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility19
Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation19
Abnormal detection in nuclear security videos based on label-specific autoencoders and reconstruction errors comparison18
Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants18
Minimum detectable activity concentration of online monitoring instrument in primary circuit of HTR-PM based on Monte Carlo simulation18
Fault injection and failure analysis on Xilinx 16 nm FinFET Ultrascale+ MPSoC18
Accounting for dependencies among performance shaping factors in SPAR-H using a regularized autoencoder and WINGS-AISM18
Evaluating the effect of wood composition on the performance of impact limiters for dry storage containers18
Design of power and phase feedback control system for ion cyclotron resonance heating in the Experimental Advanced Superconducting Tokamak18
Performance testing of a FastScan whole body counter using an artificial neural network17
The development of a fuel lifecycle reactivity control strategy for a generic micro high temperature reactor17
Nuclear power in jeopardy: The negative relationships between greenhouse gas/fine dust concerns and nuclear power acceptance in South Korea17
Rapid determination of the migration parameters of nuclides in intact granite rock under the action of electric field17
Development of a polystyrene phantom for quality assurance of a Gamma Knife®17
Performance-based drift prediction of reinforced concrete shear wall using bagging ensemble method17
Simulation and experimental analysis of aerogel's attenuation for high-energy alpha particles in fission-fusion fragment rocket applications17
Analysis of activated colloidal crud in advanced and modular reactor under pump coastdown with kinetic corrosion17
Interfacing between MAAP and MACCS to perform radiological consequence analysis17
Advancing nuclear energy forecasting: Exploring regression modeling techniques for improved accuracy17
Nano Yttrium-90 and Rhenium-188 production through medium medical cyclotron and research reactor for therapeutic usages: A Simulation study17
Development and verification of PWR core transient coupling calculation software17
Influence of operation of thermal and fast reactors of the Beloyarsk NPP on the radioecological situation in the cooling pond. Part 1: Surface water and bottom sediments16
Transient full core analysis of PWR with multi-scale and multi-physics approach16
Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests16
Fracture analysis for nozzle cracks in nuclear reactor pressure vessel using FCPAS16
Experimental investigation on effect of ion cyclotron resonance heating on density fluctuation in SOL at EAST16
The development of training platform for CiADS using cave automatic virtual environment16
Thickness measurements of a Cr coating deposited on Zr-Nb alloy plates using an ECT pancake sensor16
Thermal-hydraulic behavior simulations of the reactor cavity cooling system (RCCS) experimental facility using Flownex16
Interaction study of molten uranium with multilayer SiC/Y2O3 and Mo/Y2O3 coated graphite16
Unveiling the direct conversion X-ray sensing potential of Brucinium benzilate and N-acetylglcyine16
Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model16
Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests16
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations16
Real-time monitoring of ultra-high dose rate electron beams using bremsstrahlung photons16
Evaluating internal exposure due to intake of 131I at a nuclear medicine centre of Dhaka using bioassay methods16
Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor16
236U accelerator mass spectrometry with a time-of-flight and energy detection system16
GEOUNED: A new conversion tool from CAD to Monte Carlo geometry15
A sensitivity study on the PDFs treating uncertainties in severe accidents for pressurized heavy water reactors15
Experimental research on flow regime and transitional criterion of slug to churn-turbulent and churn-turbulent to annular flow in rectangular channels15
Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX15
Enhancing utilization and ensuring security: Insights to compromise contradicting conditions in new research reactors15
Towards automatic inspection of nuclear fuel elements in spent fuel pools: Audio analysis15
Radioactivity of biological samples of patients treated with 90Y-DOTATOC15
Improvement of doses rate prediction using the Kalman Filter-based algorithm and effective decay constant correction15
Prediction of Remaining Useful Life (RUL) of Electronic Components in the POSAFE-Q PLC Platform under NPP Dynamic Stress Conditions15
An extensive characterization of xenon isotopic activity ratios from nuclear explosion and nuclear reactors in neighboring countries of South Korea15
Experimental study on solidification of uranium tailings by microbial grouting combined with electroosmosis15
Experimental and numerical study on mechanical behavior of RC shear walls with precast steel-concrete composite module in nuclear power plant15
Development and application of the helically coiled once-through steam generator module for dynamic simulation of nuclear hybrid energy system15
An efficient seismic analysis technique for PCSG assembly using sub-structuring method and homogenization method14
Neutronics study on small power ADS loaded with recycled inert matrix fuel for transuranic elements transmutation using Serpent code14
On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating14
Micro gadolinium oxide dispersed flexible composites developed for the shielding of thermal neutron/gamma rays14
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis14
Stress-assisted oxidation behaviour of inconel 52M/316 austenitic stainless-steel dissimilar weld joints in a simulated pressurised water reactor14
External exposure specific analysis for radiation worker in reuse of containment building for Kori Unit 114
Geometrical shape and self-shielding effect of burnable poison particles on pin-in block type HTGR neutronic performance14
Acceleration of reduction of U3O8 to UO2 by particle rearrangement in a vertically-shaken bed14
Flexible liquid light-guide-based radiation sensor with LaBr3:Ce scintillator for remote gamma-ray spectroscopy14
Analysis methodology of local damage to dry storage facility structure subjected to aircraft engine crash14
Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility14
Numerical evaluation of hypothetical core disruptive accident in full-scale model of sodium-cooled fast reactor14
Numerical study on the gaseous radioactive pollutant dispersion in urban area from the upstream wind: Impact of the urban morphology14
Development of multigroup cross section library generation system TPAMS14
Cobalt(II) removal with dolomite: Use of radiotracer technique in aqueous solution14
Channel Gap Measurements of Irradiated Plate Fuel and Comparison with Post-Irradiation Plate Thickness14
Raman spectroscopy of eutectic melting between boride granule and stainless steel for sodium-cooled fast reactors14
Numerical investigation on ballooning and rupture of a Zircaloy tube subjected to high internal pressure and film boiling conditions14
The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications14
The optimum steel fiber reinforcement for prestressed concrete containment under internal pressure14
Crevice chemistry and corrosion in high temperature water: A review13
Experimental study on the retention of aerosol particles through concrete cracks under high Reynolds number flow13
Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART13
Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology13
Developing an interface strength technique using the laser shock method13
CFD modeling for hydrogen removal by a passive autocatalytic recombiner in oxygen-deficient conditions13
Localizing multiple radiation sources actively with a particle filter13
VINUS: A neutron transport solver based on the variational nodal method for reactor core analysis13
Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors13
An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code13
Removal of NOx using electron beam process with NaOH spraying13
Preliminary data analysis of surrogate fuel-loaded road transportation tests under normal conditions of transport13
Impact of geometrical parameters on SGEMP responses in cylinder model13
Operating condition optimization of liquid metal heat pipe using deep learning based genetic algorithm: Heat transfer performance13
Analytical method for determination of 41Ca in radioactive concrete13
Corrosion behavior and mechanism of CLAM and 316L steels in flowing Pb–17Li alloy under magnetic field12
Analysis of wind field data surrounding nuclear power plants to improve the effectiveness of public protective measures12
Positional correction of a 3D position-sensitive virtual Frisch-grid CZT detector for gamma spectroscopy and imaging based on a theoretical assumption12
Using water pool as cushion to mitigate ground vibration due to collapse of cooling tower with simulation of complete debris distribution12
Seismic performance evaluation of reactor containment building considering effects of concrete material models and prestressing forces12
Development of a radiological emergency evacuation model using agent-based modeling12
Radiation shielding properties of weathered soils: Influence of the chemical composition and granulometric fractions12
Strategy to coordinate actions through a plant parameter prediction model during startup operation of a nuclear power plant12
Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD12
Effect of silica fume content in concrete blocks on laser-induced explosive spalling behavior12
Experimental investigation on the effect of the rotor-stator matching mode on velocity pulsation in the centrifugal pump with a vaned diffuser12
Phase analysis of simulated nuclear fuel debris synthesized using UO2, Zr, and stainless steel and leaching behavior of the fission products and matrix elements12
CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment12
Method for clearance of contaminated buildings in Korea research reactor 1 and 212
An optimization design study of producing transuranic nuclides in high flux reactor12
Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant12
Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector12
Impedance investigation of the surface film formed on aluminum alloy exposed to nuclear reactor emergency core coolant12
Condensation oscillation characteristic of steam with non-condensable gas through multi-hole sparger at low mass flux12
Analysis of LBLOCA of APR1400 with 3D RPV model using TRACE12
2009–2022 Thailand public perception analysis of nuclear energy on social media using deep transfer learning technique12
Development of multi-physics calculation method in lead cooled fast reactor code system MOSASAUR11
Determination of k0 factors of short-lived nuclides 46mSc and 110Ag for the k0-NAA11
The volcanic aspect on determining Site of nuclear power plant in Indonesia: Gap analysis between standard and regulations11
Comparative analysis of modeling approaches for sulfide-induced corrosion of copper disposal canisters in a 3-dimensional domain11
Development and performance evaluation of large-area hybrid gamma imager (LAHGI)11
A PHITS based-computational model of a TRIGA-fueled subcritical reactor for gamma dose mapping11
Seismic performance assessment of NPP concrete containments considering recent ground motions in South Korea11
High resolution size characterization of particulate contaminants for radioactive metal waste treatment11
The role of CO on initial oxidation behavior of α-U(001) surface: A first principles study11
SiRENE: A new generation of engineering simulator for real-time simulators at EDF11
Experimental investigation and validation of TASS/SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility11
An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network11
Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity11
Study on producing radioisotopes based on fission or radiative capture method in a high flux reactor11
Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis11
Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor11
Radiation-hardened-by-design preamplifier with binary weighted current source for radiation detector11
Radioactivity analysis for EPS waste using organic solvents11
Effect of slab stiffness on floor response spectrum and fragility of equipment in nuclear power plant building11
Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark11
Development of a real-time gamma camera for high radiation fields11
Calculation of X-ray attenuation coefficients for normal and cancerous breast tissues11
A study on the dynamic characteristics of the secondary loop in nuclear power plant11
Stress evaluation method of reinforced wall-thinned Class 2/3 nuclear pipes for structural integrity assessment11
Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)11
Microstructural characteristics of a fresh U(Mo) monolithic mini-plate: Focus on the Zr coating deposited by PVD11
A surrogate model for the helium production rate in fast reactor MOX fuels11
Experiment investigation on flow characteristics of open natural circulation system11
Improvement of crossflow model of MULTID component in MARS-KS with inter-channel mixing model for enhancing analysis performance in rod bundle11
Assessment of leak-tightness for nuclear reactor containment under overpressure conditions considering aging effects11
Heat pipe type double-containment vessel as passive safety system for small modular reactors11
Optimal earthquake intensity measures for probabilistic seismic demand models of ARP1400 reactor containment building11
Thermal-hydraulic safety analysis of radioisotope production in HANARO using MCNP6 and COMSOL multiphysics: A feasibility study10
Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system10
Neutronic design and evaluation of the solid microencapsulated fuel in LWR10
Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design10
Effects of the move towards Gen IV reactors in capacity expansion planning by total generation cost and environmental impact optimization10
Experimental investigation of zinc sodium borate glass systems containing barium oxide for gamma radiation shielding applications10
Iron hydrolysis and lithium uptake on mixed-bed ion exchange resin at alkaline pH10
Tritium radioactivity estimation in cement mortar by heat-extraction and liquid scintillation counting10
Effect of gadolinium and boron addition on the texture development and magnetic properties of 23Cr–10NiCu duplex stainless steels10
Fuzzy-technique-based expert elicitation on the occurrence probability of severe accident phenomena in nuclear power plants10
A simplified SP3 NEM solver within a unified formulation for pin-by-pin core multi-group calculations10
Efficiency calibration and coincidence summing correction for a NaI(Tl) spherical detector10
Possibility of curium as a fuel for VVER-1200 reactor10
Classification of nuclear activity types for neighboring countries of South Korea using machine learning techniques with xenon isotopic activity ratios10
Experiment of proof-of-principle on prompt gamma-positron emission tomography (PG-PET) system for in-vivo dose distribution verification in proton therapy10
Optimizing irradiation conditions for natural molybdenum in WWR-K reactor10
Manipulation and diagnosis of femtosecond relativistic electron bunch using terahertz-driven resonators10
Nodal method for handling irregularly deformed geometries in hexagonal lattice cores10
Rare earth elements as tracers: A study on post-wildfire effects in soil by neutron activation analysis10
Numerical analysis to determine fire suppression time for multiple water mist nozzles in a large fire test compartment10
Comparative analysis of internal flow characteristics of LBE-cooled fast reactor main coolant pump with different structures under reverse rotation accident conditions10
Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents10
The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation10
Patent mining and diversity assessment of nuclear power technologies10
A radioactive source-seeking method based on angle constraint and particle diffusion10
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