Annals of Nuclear Energy

Article	Citations
Recent progress of CFD applications in PWR thermal hydraulics study and future directions	135
Py-MLBUF: Development of an online-platform for gamma-ray shielding calculations and investigations	67
Technological solutions for long-term storage of partially used nuclear waste: A critical review	63
Molten salt for advanced energy applications: A review	59
Heat pipe failure accident analysis in megawatt heat pipe cooled reactor	54
Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis	48
Two decades on human reliability analysis: A bibliometric analysis and literature review	43
Fault identification and diagnosis based on KPCA and similarity clustering for nuclear power plants	42
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review	42
Improved PCA model for multiple fault detection, isolation and reconstruction of sensors in nuclear power plant	41
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods	40
Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor	40
MCS – A Monte Carlo particle transport code for large-scale power reactor analysis	40
Review of thermophysical property methods applied to fueled and un-fueled molten salts	39
A fuzzy-PID composite controller for core power control of liquid molten salt reactor	38
NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems	36
Progress in studying the fretting wear/corrosion of nuclear steam generator tubes	36
Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization	35
Cold spray technology in nuclear energy applications: A review of recent advances	34
Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review	33
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%	33
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors	32
Diagnosis of operational failures and on-demand failures in nuclear power plants: An approach based on dynamic Bayesian networks	32
A data-driven adaptive fault diagnosis methodology for nuclear power systems based on NSGAII-CNN	32
Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly	31

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	31
Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system	31
A high-order and efficient numerical technique for the nonlocal neutron diffusion equation representing neutron transport in a nuclear reactor	30
Implementation of Grey Wolf Optimization (GWO) algorithm to multi-objective loading pattern optimization of a PWR reactor	30
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	30
Investigation on effects of Fluid-Structure-Interaction (FSI) on the lubrication performances of water lubricated bearing in primary circuit loop system of nuclear power plant	30
A new approach for fault diagnosis with full-scope simulator based on state information imaging in nuclear power plant	29
A functional variable universe fuzzy PID controller for load following operation of PWR with the multiple model	29
Highly efficient elimination of uranium from wastewater with facilely synthesized Mg-Fe layered double hydroxides: Optimum preparation conditions and adsorption kinetics	28
A digital twin approach to system-level fault detection and diagnosis for improved equipment health monitoring	28
Wall temperature prediction at critical heat flux using a machine learning model	27
Application of machine learning methods to predict a thermal conductivity model for compacted bentonite	27
Analysis of double-layered buffer in high-level waste repository	25
Preliminary design of the I2S-LWR containment system	25
An assembly-level neutronic calculation method based on LightGBM algorithm	25
Nuclear Power Plant accident identification system with “don’t know” response capability: Novel deep learning-based approaches	25
Physics-informed neural networks for the point kinetics equations for nuclear reactor dynamics	25
Development of a bypass control strategy for supercritical CO2 Brayton cycle cooled reactor system under load-following operation	24
Results from a multi-physics numerical benchmark for codes dedicated to molten salt fast reactors	24
Investigation on corium spreading over ceramic and concrete substrates in VULCANO VE-U7 experiment with moving particle semi-implicit method	23
Research on fast intelligence multi-objective optimization method of nuclear reactor radiation shielding	23
Development and assessment of a nearly autonomous management and control system for advanced reactors	23
Utilization of random forest classifier and artificial neural network for predicting the acceptance of reopening decommissioned nuclear power plant	23
The use of multi-objective optimization to improve the design process of nuclear power plant systems	22
Multi-objective optimization method for nuclear reactor radiation shielding design based on PSO algorithm	22
Underwater laser cutting of stainless steel up to 100 mm thick for dismantling application in nuclear power plants	22
Back propagation (BP) neural network prediction and chaotic characteristics analysis of free falling liquid film fluctuation on corrugated plate wall	22
Numerical investigation on performance of moisture separator: Experimental validation, applications and new findings	22
A methodology for diagnosing FAC induced pipe thinning using accelerometers and deep learning models	22
Pre-trained network-based transfer learning: A small-sample machine learning approach to nuclear power plant classification problem	22
Extended state observer-based adaptive dynamic sliding mode control for power level of nuclear power plant	22
Passive decay heat removal system design for the integral inherent safety light water reactor (I2S-LWR)	22
SINBAD – Radiation shielding benchmark experiments	21
Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition	21
Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System)	21
Experimental study of droplet impacting on inclined wetted wall in corrugated plate separator	21
Three-dimensional thermal–hydraulic coupled analysis in the nuclear waste repository	21
Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation	21
Crack fault diagnosis of rotating machine in nuclear power plant based on ensemble learning	21
Thermal-hydraulic performance of a PCHE with sodium and sCO2 as working fluids	20
Development of a flow sweeping mixing model for helical fuel rod bundles	20
Current state of partitioning and transmutation studies for advanced nuclear fuel cycles	20
Robust optimal-integral sliding mode control for a pressurized water nuclear reactor in load following mode of operation	20
Depletion capabilities in the OpenMC Monte Carlo particle transport code	20
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests	20
Water hammer analysis when switching of parallel pumps based on contra-motion check valve	20
Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)	20
An investigation of pressure build-up effects due to check valve’s closing characteristics using dynamic mesh techniques of CFD	19
Analysis of liquid droplet impacting on liquid film by CLSVOF	19
X2 VVER-1000 benchmark revision: Fresh HZP core state and the reference Monte Carlo solution	19

Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore	19
Rod bundle thermal-hydraulics experiment with water and water-Al	19
Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system	19
A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors	19
A novel approach in exergy optimization of a WWER1000 nuclear power plant using whale optimization algorithm	19
Experimental measurements of flow mixing in cold leg of a pressurized water reactor	19
Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR)	19
An inverse-distance-based fitting term for 3D-Var data assimilation in nuclear core simulation	18
Development of a generative-adversarial-network-based signal reconstruction method for nuclear power plants	18
Development of a diagnostic algorithm for abnormal situations using long short-term memory and variational autoencoder	18
PCA-SVM method with sliding window for online fault diagnosis of a small pressurized water reactor	18
A time and frequency domain analysis of the effect of vibrating fuel assemblies on the neutron noise	18
Numerical investigation on performance of moisture separator by Lagrangian-Eulerian strategy: Physical mechanisms, theoretical models, and advanced algorithms	18
Ensemble learning with diversified base models for fault diagnosis in nuclear power plants	18
Defect detection of nuclear fuel assembly based on deep neural network	18
An efficient digital twin based on machine learning SVD autoencoder and generalised latent assimilation for nuclear reactor physics	18
A reference neutron field for measurement of spectrum averaged cross sections	18
The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units	18
Feature extraction for early fault detection in rotating machinery of nuclear power plants based on adaptive VMD and Teager energy operator	18
Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion	18
Geometry design and performance optimization of a terrestrial radioisotope thermoelectric generator based on finite element analysis	18
The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion	18
Two-phase flow boiling instabilities: A review	18
LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method	18
Secure embedded intelligence in nuclear systems: Framework and methods	18
Performance shaping factor taxonomy for human reliability analysis on mitigating nuclear power plant accidents caused by extreme external hazards	17
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	17
A nonintrusive adaptive reduced order modeling approach for a molten salt reactor system	17
On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics	17
A mixed intelligent condition monitoring method for nuclear power plant	17
Thermal conductivity of bentonite-graphite mixture and its prediction for high-level radioactive waste repository	17
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	16
The effect of grid generated turbulence on the fluidelastic instability response in parallel triangular tube array	16
Immobilization of iodine waste forms: A low-sintering temperature with Bi2O3-B2O3-ZnO glass	16
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction	16
A POD reduced-order model for resolving the neutron transport problems of nuclear reactor	16
Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly	16
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	16
Experimental study on the separation performance of a full-scale SG steam-water separator	16
Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis	16
Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF	16
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic	16
Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT	15
Thermal-and fast-spectrum molten salt reactors for minor actinides transmutation	15
Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator	15
Study on switching control of PWR core power with a fuzzy multimodel	15
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	15
Review of the tube external condensation heat transfer characteristic of the passive containment cooling system in nuclear power plant	15
A comparative study of deep learning-based fault diagnosis methods for rotating machines in nuclear power plants	15
Sensitivity analysis based on Morris method of passive system performance under ocean conditions	15
CORE SIM+: A flexible diffusion-based solver for neutron noise simulations	15
Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm	15
Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor	15
Numerical study on the heat transfer deterioration and its mitigations for supercritical CO2 flowing in a horizontal miniature tube	15
Research on robustness of five typical data-driven fault diagnosis models for nuclear power plants	15
Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl	15
Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method	15
A novel multi-objective shielding optimization method: DNN-PCA-NSGA-Ⅱ	15
Strategies for thorium fuel cycle transition in the SD-TMSR	15
LQGI/LTR based robust control technique for a pressurized water nuclear power plant	15
A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection	15
Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles	15
Dynamic reliability analysis framework for passive safety systems of Nuclear Power Plant	15
A sequential conjugate gradient method to estimate heat flux for nonlinear inverse heat conduction problem	15
Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model	15
Minimum collective dose based optimal evacuation path-planning method under nuclear accidents	15
VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods	15
Numerical study on convective heat transfer and friction characteristics of molten salts in circular tubes	15
Intensified single-phase forced convective heat transfer with helical-twisted tube in coil heat exchangers	15
Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle	14
Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor	14
Design and exergy evaluation of a novel parabolic trough solar-nuclear combined system	14
Radiation dose consequences of postulated limiting accidents in small modular reactors to inform emergency planning zone size requirements	14
Application of Kriging and Variational Bayesian Monte Carlo method for improved prediction of doped UO2 fission gas release	14
Prediction of unmeasurable parameters of NPPs using different model-free methods based on cross-correlation detection of measurable/unmeasurable parameters: A comparative study	14
Multiscale thermal-hydraulic modeling of the pebble bed fluoride-salt-cooled high-temperature reactor	14
Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator	14
PWR core loading pattern optimization with adaptive genetic algorithm	14
A multiphase MPS method coupling fluid–solid interaction/phase-change models with application to debris remelting in reactor lower plenum	14
Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials	14

Neutronic design study of an integrated space nuclear reactor with Stirling engine	14
A design of switching supervisory control based on fuzzy-PID controllers for VVER-1000 pressurizer system with RELAP5 and MATLAB coupling	14
Improved adaptive variance reduction algorithm based on RMC code for deep penetration problems	14
A deep transfer learning method for system-level fault diagnosis of nuclear power plants under different power levels	14
Development and verification of a methodology for neutron noise response to fuel assembly vibrations	14
A fuzzy-PID series feedback self-tuned adaptive control of reactor power using nonlinear multipoint kinetic model under reference tracking and disturbance rejection	14
Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode	14
Application of a new OpenFOAM-based neutron diffusion kinetics solver to pebble-type VHTRs	14
Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings	14
Flow boiling heat transfer under marine motions: A comprehensive review	14
Model based security verification of Cyber-Physical System based on Petrinet: A case study of Nuclear power plant	14
Large-scale design optimisation of boiling water reactor bundles with neuroevolution	13
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems	13
Load-following control of nuclear reactors based on fuzzy input-output model	13
CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4)	13
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	13
Investigating the Performance and safety features of Pressurized water reactors using the burnable poisons	13
A multi-stage hybrid fault diagnosis approach for operating conditions of nuclear power plant	13
Which nuclear data can be validated with LLNL pulsed-sphere experiments?	13
A probabilistic model-based diagnostic framework for nuclear engineering systems	13
Supercritical CO2 flow instability in natural circulation loop: CFD analysis	13
Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program	13
Verification of the 3D capability of OpenMOC with the C5G7 3D extension benchmark	13
Evaluation of photon shielding properties for new refractory tantalum-rich sulfides Ta9(XS3)2 alloys: A study with the MCNP-5	13
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	13
Fault diagnosis based on conditional generative adversarial networks in nuclear power plants	13
Development of the Machine Learning-based Safety Significant Factor Inference Model for Diagnosis in Autonomous Control System	13
Main outcomes from the IVR code benchmark performed in the European IVMR project	13
Decontamination of concrete waste from nuclear power plant decommissioning in South Korea	13
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way	13
Development and verification of the coupled thermal–hydraulic code – TRACE/SCF based on the ICoCo interface and the SALOME platform	12
Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid Sodium pump system	12
Analysis of the flow noises of the nuclear main pump caused by the high temperature liquid Sodium in the two-circuit main loop liquid Sodium pump system	12
Nuclear data evaluation augmented by machine learning	12
Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis	12
CFD investigation for a 7-pin wire-wrapped fuel assembly with different shapes of fuel duct wall	12
An internal parallel coupling method based on NECP-X and CTF and analysis of the impact of thermal-hydraulic model to the high-fidelity calculations	12
A mechanistic bubble crowding model for predicting critical heat flux in subchannels of a bundle	12
Distributed-parallel CFD computation for all fuel assemblies in PWR core	12
Finite difference Jacobian based Newton-Krylov coupling method for solving multi-physics nonlinear system of nuclear reactor	12
Review on sensors to measure control rod position for nuclear reactor	12
Application of Cuckoo Search algorithm to Loading Pattern Optimization problems	12
Periodic magnetohydrodynamic mixed convection flow along a cone embedded in a porous medium with variable surface temperature	12
Subchannel analysis of annular fuel assembly using the preconditioned Jacobian-free Newton Krylov methods	12
Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage	12
Deep learning schemes for event identification and signal reconstruction in nuclear power plants with sensor faults	12
Three-dimensional thermal hydraulic transient calculation of coupled cold and hot sodium pools under a loss of feedwater accident in the China experimental fast reactor	12
Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation	12
Observer based adaptive robust Feedback-linearization control for VVER-1000 nuclear reactors with bounded axial power distribution based on the validated multipoint kinetics reactor model	12
Thermal-hydraulic analysis of pellet bed reactor for space nuclear electric propulsion	12
Numerical analysis of liquid metal helical coil once-through tube steam generator	12
Effect of precipitates on hardening of 17-4PH martensitic stainless steel serviced at 300 °C in nuclear power plant	12
A two-phase three-field modeling framework for heat pipe application in nuclear reactors	12
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case	12
Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor	12
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	12
Development and verification of a simulation toolkit for Self-Powered Neutron Detector	12
Characterization of high-temperature nuclear fuel-coolant interactions through X-ray visualization and image processing	12
Preliminary uncertainty and sensitivity analysis of the Molten Salt Fast Reactor steady-state using a Polynomial Chaos Expansion method	11
A morphological image processing method for simultaneous scrutinization of particle position and velocity in pebble flow	11
Development of coupled PROTEUS-NODAL and SAM code system for multiphysics analysis of molten salt reactors	11
Multi-robot collaborative radioactive source search based on particle fusion and adaptive step size	11
A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis	11
A quantitative assessment framework for cyber-attack scenarios on nuclear power plants using relative difficulty and consequence	11
Experimental research on steam condensation in presence of non-condensable gas under high pressure	11
Internal model control based proportional-integral controller with class topper optimization for power control of molten salt breeder reactor core	11
Experimental study on flow modes and transient characteristics in low-pressure equal-height-difference natural circulation system	11
An online operator support tool for severe accident management in nuclear power plants using dynamic event trees and deep learning	11
A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0	11
Experimental study on sloshing characteristics in a pool with stratified liquids	11
The safety improvement of VVER-1000 NPP against SBO accident using portable air-cooled diesel generator	11
Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes	11
Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR	11
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	11
OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW	11
A multiphysics model of the versatile test reactor based on the MOOSE framework	11
Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo	11
AI-Guided Reasoning-Based Operator Support System for the Nuclear Power Plant Management	11
A mini-review on population balance model for gas-liquid subcooled boiling flow in nuclear industry	11
Experimental study on flow structures of central blockage accidents in a rectangular channel using PIV and POD	11
Sub-channel analysis of lead–bismuth fast reactor fuel assembly with wire spacers for China initiative accelerator driven system	11
Reliability assessment of passive systems using artificial neural network based response surface methodology	11
Neutron clustering as a driver of Monte Carlo burn-up instability	11
A dynamic model of xenon behavior in the Molten Salt Reactor Experiment	11
Hazard analysis for identifying common cause failures of digital safety systems using a redundancy-guided systems-theoretic approach	11
Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review	11
Novel design integration for advanced nuclear heat-pipe systems	11
Analysis for the ARIANE GU1 sample: Nuclide inventory and decay heat	11
Coupled Monte Carlo and thermal-fluid modeling of high temperature gas reactors using Cardinal	11
Numerical study of natural convection effects on effective thermal conductivity in a pebble bed	11
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	11
SCALE capabilities for high temperature gas-cooled reactor analysis	11
A research and development review of water-cooled breeding blanket for fusion reactors	11
CFD analysis on flow and heat transfer characteristic in natural circulation system with subchannels under rolling conditions	11
Review on separation mechanism of corrugated plate separator	11