Annals of Nuclear Energy

Article	Citations
Recent progress of CFD applications in PWR thermal hydraulics study and future directions	156
Molten salt for advanced energy applications: A review	97
Technological solutions for long-term storage of partially used nuclear waste: A critical review	83
Py-MLBUF: Development of an online-platform for gamma-ray shielding calculations and investigations	74
Heat pipe failure accident analysis in megawatt heat pipe cooled reactor	59
Two decades on human reliability analysis: A bibliometric analysis and literature review	53
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review	49
Fault identification and diagnosis based on KPCA and similarity clustering for nuclear power plants	49
Improved PCA model for multiple fault detection, isolation and reconstruction of sensors in nuclear power plant	48
NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems	47
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods	44
Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization	43
Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review	43
Cold spray technology in nuclear energy applications: A review of recent advances	42
Second law analysis of a 3D magnetic buoyancy-driven flow of hybrid nanofluid inside a wavy cubical cavity partially filled with porous layer and non-Newtonian layer	41
A data-driven adaptive fault diagnosis methodology for nuclear power systems based on NSGAII-CNN	40
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors	38
Implementation of Grey Wolf Optimization (GWO) algorithm to multi-objective loading pattern optimization of a PWR reactor	37
A digital twin approach to system-level fault detection and diagnosis for improved equipment health monitoring	36
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	34
Study on reduction of pressure oscillation in low-velocity steam jet condensation	32
Development of a flow sweeping mixing model for helical fuel rod bundles	32
An efficient digital twin based on machine learning SVD autoencoder and generalised latent assimilation for nuclear reactor physics	32
Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly	31
A high-order and efficient numerical technique for the nonlocal neutron diffusion equation representing neutron transport in a nuclear reactor	31

Two-phase flow boiling instabilities: A review	30
Depletion capabilities in the OpenMC Monte Carlo particle transport code	30
Development of a bypass control strategy for supercritical CO2 Brayton cycle cooled reactor system under load-following operation	29
Physics-informed neural networks for the point kinetics equations for nuclear reactor dynamics	28
An assembly-level neutronic calculation method based on LightGBM algorithm	28
Pre-trained network-based transfer learning: A small-sample machine learning approach to nuclear power plant classification problem	28
SINBAD – Radiation shielding benchmark experiments	28
Development and assessment of a nearly autonomous management and control system for advanced reactors	27
VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods	27
Evaluation of photon shielding properties for new refractory tantalum-rich sulfides Ta9(XS3)2 alloys: A study with the MCNP-5	27
Research on fast intelligence multi-objective optimization method of nuclear reactor radiation shielding	27
Multi-objective optimization method for nuclear reactor radiation shielding design based on PSO algorithm	27
Periodic magnetohydrodynamic mixed convection flow along a cone embedded in a porous medium with variable surface temperature	26
Utilization of random forest classifier and artificial neural network for predicting the acceptance of reopening decommissioned nuclear power plant	26
Analysis of double-layered buffer in high-level waste repository	26
Robust optimal-integral sliding mode control for a pressurized water nuclear reactor in load following mode of operation	25
Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition	25
Underwater laser cutting of stainless steel up to 100 mm thick for dismantling application in nuclear power plants	25
Development of a diagnostic algorithm for abnormal situations using long short-term memory and variational autoencoder	25
Thermal-hydraulic performance of a PCHE with sodium and sCO2 as working fluids	24
Thermal conductivity of bentonite-graphite mixture and its prediction for high-level radioactive waste repository	24
Current state of partitioning and transmutation studies for advanced nuclear fuel cycles	24
Crack fault diagnosis of rotating machine in nuclear power plant based on ensemble learning	24
Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor	24
LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method	24
Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system	23
Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion	23
Three-dimensional thermal–hydraulic coupled analysis in the nuclear waste repository	23
An investigation of pressure build-up effects due to check valve’s closing characteristics using dynamic mesh techniques of CFD	23
Back propagation (BP) neural network prediction and chaotic characteristics analysis of free falling liquid film fluctuation on corrugated plate wall	23
Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation	22
Supercritical CO2 flow instability in natural circulation loop: CFD analysis	22
A comparative study of deep learning-based fault diagnosis methods for rotating machines in nuclear power plants	22
Rod bundle thermal-hydraulics experiment with water and water-Al	22
Feature extraction for early fault detection in rotating machinery of nuclear power plants based on adaptive VMD and Teager energy operator	21
Predicting and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters in the NuScale nuclear reactor using nanofluid as a coolant via machine learning methods through GA, PSO	21
Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials	21
Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis	21
PCA-SVM method with sliding window for online fault diagnosis of a small pressurized water reactor	21
Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl	20
Strategies for thorium fuel cycle transition in the SD-TMSR	20
Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle	20
Review of the tube external condensation heat transfer characteristic of the passive containment cooling system in nuclear power plant	20
Geometry design and performance optimization of a terrestrial radioisotope thermoelectric generator based on finite element analysis	20
Numerical study on the heat transfer deterioration and its mitigations for supercritical CO2 flowing in a horizontal miniature tube	20
Fault diagnosis based on conditional generative adversarial networks in nuclear power plants	20
Research on robustness of five typical data-driven fault diagnosis models for nuclear power plants	19
Data-driven machine learning for disposal of high-level nuclear waste: A review	19
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way	19
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	19

The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units	19
Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes	19
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	19
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction	19
A sequential conjugate gradient method to estimate heat flux for nonlinear inverse heat conduction problem	19
Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings	19
Ensemble learning with diversified base models for fault diagnosis in nuclear power plants	19
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic	19
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	18
A POD reduced-order model for resolving the neutron transport problems of nuclear reactor	18
A fuzzy-PID series feedback self-tuned adaptive control of reactor power using nonlinear multipoint kinetic model under reference tracking and disturbance rejection	18
Effect of precipitates on hardening of 17-4PH martensitic stainless steel serviced at 300 °C in nuclear power plant	18
Coupled Monte Carlo and thermal-fluid modeling of high temperature gas reactors using Cardinal	18
Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator	18
Nuclear data evaluation augmented by machine learning	18
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	18
A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection	18
LQGI/LTR based robust control technique for a pressurized water nuclear power plant	17
Characterization of high-temperature nuclear fuel-coolant interactions through X-ray visualization and image processing	17
Minimum collective dose based optimal evacuation path-planning method under nuclear accidents	17
Intensified single-phase forced convective heat transfer with helical-twisted tube in coil heat exchangers	17
CORE SIM+: A flexible diffusion-based solver for neutron noise simulations	17
Large-scale design optimisation of boiling water reactor bundles with neuroevolution	17
A deep transfer learning method for system-level fault diagnosis of nuclear power plants under different power levels	17
A multiphase MPS method coupling fluid–solid interaction/phase-change models with application to debris remelting in reactor lower plenum	17
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	17
Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor	16
Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles	16
Application of a new OpenFOAM-based neutron diffusion kinetics solver to pebble-type VHTRs	16
A multi-stage hybrid fault diagnosis approach for operating conditions of nuclear power plant	16
A novel multi-objective shielding optimization method: DNN-PCA-NSGA-Ⅱ	16
Experimental study on flow modes and transient characteristics in low-pressure equal-height-difference natural circulation system	16
Research on anomaly detection method of nuclear power plant operation state based on unsupervised deep generative model	16
PWR core loading pattern optimization with adaptive genetic algorithm	16
Thermal-and fast-spectrum molten salt reactors for minor actinides transmutation	16
Decontamination of concrete waste from nuclear power plant decommissioning in South Korea	16
Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF	16
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor	16
Review of nuclear power plant control research: Neural network-based methods	16
Development and verification of a methodology for neutron noise response to fuel assembly vibrations	16
The effect of grid generated turbulence on the fluidelastic instability response in parallel triangular tube array	16
Numerical analysis of liquid metal helical coil once-through tube steam generator	16
Application of Weighted Linear Combination approach in a Geographical Information System environment for nuclear power plant site selection: the case of Ghana	16
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	16
Immobilization of iodine waste forms: A low-sintering temperature with Bi2O3-B2O3-ZnO glass	16
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems	16
Influence mechanism of the non-uniform inflow on performance of reactor coolant pump	16
Stochastic procedures to solve the nonlinear mass and heat transfer model of Williamson nanofluid past over a stretching sheet	15
Load-following control of nuclear reactors based on fuzzy input-output model	15
Parameter identification and state estimation for nuclear reactor operation digital twin	15
Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor	15
Comparison on the thermal–hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation	15
Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR)	15
Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5	15
Review of interdisciplinary heat transfer enhancement technology for nuclear reactor	15
Identification of the appropriate architecture of multilayer feed-forward neural network for estimation of NPPs parameters using the GA in combination with the LM and the BR learning algorithms	15
A design of switching supervisory control based on fuzzy-PID controllers for VVER-1000 pressurizer system with RELAP5 and MATLAB coupling	15
SCALE capabilities for high temperature gas-cooled reactor analysis	15
NSGA-II algorithm-based LQG controller design for nuclear reactor power control	15
Development and verification of the coupled thermal–hydraulic code – TRACE/SCF based on the ICoCo interface and the SALOME platform	15
Application of Kriging and Variational Bayesian Monte Carlo method for improved prediction of doped UO2 fission gas release	15
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	15
Experimental research on steam condensation in presence of non-condensable gas under high pressure	15
CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4)	14
Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR	14
Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis	14
A probabilistic model-based diagnostic framework for nuclear engineering systems	14
A multiple-architecture deep learning approach for nuclear power plants accidents classification including anomaly detection and “don’t know” response	14
Development and verification of a simulation toolkit for Self-Powered Neutron Detector	14
Experimental study on flow structures of central blockage accidents in a rectangular channel using PIV and POD	14
A multiphysics model of the versatile test reactor based on the MOOSE framework	14
Deep learning schemes for event identification and signal reconstruction in nuclear power plants with sensor faults	14
Development of a fast thermal-hydraulic model to simulate heat and fluid flow in MNSR	14
Development of the Machine Learning-based Safety Significant Factor Inference Model for Diagnosis in Autonomous Control System	14
A fault diagnosis of nuclear power plant rotating machinery based on multi-sensor and deep residual neural network	14
A two-phase three-field modeling framework for heat pipe application in nuclear reactors	14
Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review	14
On the importance of target accuracy assessments and data assimilation for the co-development of nuclear data and fast reactors: MYRRHA and ESFR	14
Model based security verification of Cyber-Physical System based on Petrinet: A case study of Nuclear power plant	14
Implementation of two-phase gas transport into VERA for molten salt reactor analysis	14

Finite difference Jacobian based Newton-Krylov coupling method for solving multi-physics nonlinear system of nuclear reactor	13
Optimization of neutron tracking algorithms for GPU-based continuous energy Monte Carlo calculation	13
Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method	13
A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis	13
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	13
Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results	13
Research on stability characteristics of a spring-loaded valve with two outlets	13
Internal model control based proportional-integral controller with class topper optimization for power control of molten salt breeder reactor core	13
Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor	13
Which nuclear data can be validated with LLNL pulsed-sphere experiments?	13
A mini-review on population balance model for gas-liquid subcooled boiling flow in nuclear industry	13
Prediction of critical heat flux using Gaussian process regression and ant colony optimization	13
Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM	13
Transient thermal–hydraulic analysis of SCO2-cooled reactor system with modified RELAP5	13
Multi-robot collaborative radioactive source search based on particle fusion and adaptive step size	13
An improved zigzag-type printed circuit heat exchanger for supercritical CO2 Brayton cycles	13
Surrogate modeling for neutron diffusion problems based on conservative physics-informed neural networks with boundary conditions enforcement	13
Separation efficiency theoretical model of swirl-vane separator based on bidirectional vortex	12
Effect of cooling schemes on performance of MW-class space nuclear closed Brayton cycle	12
Development and validation of PROTEUS-NODAL transient analyses capabilities for molten salt reactors	12
ADS design concept for disposing of the U.S. spent nuclear fuel inventory	12
Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation	12
Neutronic modeling of megawatt-class heat pipe reactors	12
The cavitation performance analysis of the RCP under LBLOCA at inlet	12
Two-phase modeling of water-air flow of dispersed and segregated flows	12
Advanced flow and temperature measurements in a forced convection molten salt test loop	12
Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel	12
Development and application of Monte Carlo and COMSOL coupling code for neutronics/thermohydraulics coupled analysis	12
Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark	12
OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW	12
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	12
An efficient numerical method for fractional neutron diffusion equation in the presence of different types of reactivities	12
Rapid source term prediction in nuclear power plant accidents based on dynamic Bayesian networks and probabilistic risk assessment	12
Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions	12
Sub-channel analysis of lead–bismuth fast reactor fuel assembly with wire spacers for China initiative accelerator driven system	12
Numerical investigation of dynamic characteristics of debris bed formation based on CFD-DEM method	12
Discrete element simulation of Pebble Bed Reactors on graphics processing units	12
Site selection for radioactive waste disposal facility by GIS based multi criteria decision making	12
Experimental investigation of underwater laser cutting for thick stainless steel plates using a 6-kW fiber laser	12
Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid	12
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	12
Investigation of Anderson acceleration in neutronics-thermal hydraulics coupled direct whole core calculation	12
Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals	12
Seismic response correlation coefficient for the structures, systems and components of the Korean nuclear power plant for seismic probabilistic safety assessment	12
CFD analysis on flow and heat transfer characteristic in natural circulation system with subchannels under rolling conditions	12
Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid Sodium pump system	12
Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using Thermal hydraulic and neutronic analysis by implementing the gen	12
Development of coupled PROTEUS-NODAL and SAM code system for multiphysics analysis of molten salt reactors	12
Hazard analysis for identifying common cause failures of digital safety systems using a redundancy-guided systems-theoretic approach	12
Experimental research on droplets releasing characteristics of the bubble bursting behavior at a free surface with an aerosol	11
Sub-channel code development of lead-bismuth eutectic fast reactor available for multiple fuel assembly structures	11
Investigate the possibility of burning weapon-grade plutonium using a concentric rods BS assembly of VVER-1200	11
Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient	11
Effects of the 3-D wall structures on the flow and mixing characteristics of pebbles in pebble beds in HTR-10	11
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F	11
Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels	11
CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel	11
A Collision-based Domain Decomposition scheme for large-scale depletion with the Serpent 2 Monte Carlo code	11
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs	11
Fractional two energy groups matrix representation for nuclear reactor dynamics with an external source	11
Comparison of machine learning models for the detection of partial defects in spent nuclear fuel	11
Many-objective rapid optimization of reactor shielding design based on NSGA - III	11
Detection and estimation of faulty sensors in NPPs based on thermal-hydraulic simulation and feed-forward neural network	11
The scaling technology in nuclear reactor thermal hydraulic	11
Loose parts detection method combining blind deconvolution with support vector machine	11
Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system	11
Thermochemical changes on swelling pressure of compacted bentonite	11
Modeling of the droplet entrainment rate in the post-dryout regime for the analysis of a reflood phase	11
Development of fault diagnosis for nuclear power plant using deep learning and infrared sensor equipped UAV	11
AI-Guided Reasoning-Based Operator Support System for the Nuclear Power Plant Management	11
Prediction of the internal states of a nuclear power plant containment in LOCAs using rule-dropout deep fuzzy neural networks	11
A robust strategy for sensor fault detection in nuclear power plants based on principal component analysis	11
A morphological image processing method for simultaneous scrutinization of particle position and velocity in pebble flow	11
An improvement to the Kalos’ formula for double layer gamma ray exposure buildup factors for shielding materials of nuclear and radiological facilities	11
A nodal sensitivity study of MELCOR simulation for severe accidents in a pressurized water reactor	11
Analysis for the ARIANE GU1 sample: Nuclide inventory and decay heat	11
Noise optimization of multi-stage orifice plates based on RBF neural network response surface and adaptive NSGA-II	11
A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults	11
Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method	11
Numerical investigation of thermal hydraulic behaviors in wire-wrapped bundle with smaller wire diameter of peripheral rods	11
Hydrothermal-processed volcanic ash-based geopolymers for immobilization of sodium salt wastes containing Cs	11
Experimental investigation on flashing-induced flow instability in a natural circulation scaled-down test facility	11
Effect of impact velocity on time-dependent force and droplet pressure in high-speed liquid droplet impingement	11
Experimental research on the characteristics of steam jet condensation in subcooled water through a double-hole nozzle in one direction	11
Operation and safety analysis of space lithium-cooled fast nuclear reactor	11
Hybrid Monte Carlo methods for Geant4-based nuclear well logging implementation	11
Application of deep neural network for generating resonance self-shielded cross-section	11
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)	11
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	11
Species transport analysis of noble metal fission product transport, deposition, and extraction in the molten salt reactor experiment	11
A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system	11
A neural network predictive control method for power control of small pressurized water reactors	11
Affine reduced-order model for radiation transport problems in cylindrical coordinates	11
Availability analysis of safety-critical and control systems of NPP using stochastic modeling	10
A continuous learning monitoring strategy for multi-condition of nuclear power plant	10