Annals of Nuclear Energy

Article	Citations
Editorial Board	84
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	76
Radiation survey for Taiwan research reactor vessel	71
Impact of experimental effects on a resolved resonance evaluation for practical applications	68
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	64
Development of lumped-parameter models for debris bed remelting analysis	60
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	52
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	48
Neutron transmission measurements for silica glass at the KURNS-LINAC	48
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	47
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	46
Editorial Board	46
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	45
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	45
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	45
Editorial Board	44
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	44
Development and verification of the hexagonal core simulation capability of the NECP-X code	43
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	42
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	41
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	41
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	40
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	40
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	39
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	39

Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	38
Variable universe fuzzy control of once-through steam generator feedwater	37
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	37
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	37
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	36
Investigation of environmental effects from the operation of a nuclear power plant	36
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	35
Transient performance evaluation of passive residual heat removal system in liquid molten salt reactor	35
Impact of deposition morphology on critical heat flux during pool boiling from horizontal tubes	35
Development and improvement of the quadratic depletion method	34
A compact Double-spiral electromagnetic pump for liquid metal cooling	33
Dynamic mode decomposition for subcriticality measurement using measured data at single location	32
Effects of two-dimensional hills combination with distance variation on the aerosols dispersion based on wind tunnel experiment	31
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	31
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	31
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	30
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	29
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	29
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	28
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	28
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	28
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	27
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	27
Mapping radioactive environments by use of sparse Gaussian processes regression	27
A Bayesian Network-based system framework for seismic resilience assessment of nuclear power plants	27
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	26
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	26
The measurement of the 86Kr(n,2n)85mKr reaction cross section for the d-T neutrons	26
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	26
A molten salt test loop for component and instrumentation testing	26
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	26
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	25
Research on sensor fault tolerance technology in nuclear power plant control system	25
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	25
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	24
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	24
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	24
Modelling of the expansion phase of Sodium fast reactor severe accident	24
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	24
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	24
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	24
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	24
A deep-learning representation of multi-group cross sections in lattice calculations	23
Development of a decommissioning waste assessment module for heavy water reactors	23
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	23
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	23
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	23
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	23
CFD simulation and wind tunnel investigation of atmospheric radionuclide dispersion around a nuclear power plant	22
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	22

Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	22
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	22
Development of a diffusive simplified double P22
Neutron transmission measurement of thick n	22
Experimental and numerical study of an innovative twined tube HX design	22
Free convective condensation in the presence of noncondensable gases − A review with heat transfer studies	21
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	21
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	21
Case study of flow instabilities in subchannels via multidimensional CFD approach	21
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	21
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor	21
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	21
Editorial Board	21
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	21
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	21
CFD analysis on the safety performance of CSNS solid target under a postulated large loss of coolant accident	21
Editorial Board	20
Analysis and enhancements of the coolant velocity estimation method in PWR core	20
Criticality safety of fuel assemblies with missing fuel rods	20
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	20
Editorial Board	20
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	20
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	20
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	20
Editorial Board	20
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	19
An improved spatial-dependent model of neutron multiplicity counting for large-volume plutonium solution	19
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	19
Impact of isotopic and compositional gradients on the performance of nuclear fuel elements enabled by additive manufacturing	19
Editorial Board	19
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	19
χ-19
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	19
Special issue: “In honour of the cowboy who has been riding the wide prairies of neutron transport for more than fifty years”	19
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	19
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	19
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	19
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	18
A study on friction factor correlation considering the torsion effect in helical pipe flow	18
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	18
Wavelet-based angular discretization finite difference method for neutron transport equation solving	18
A simulation study on the thermal stratification characteristics induced by natural convection produced by cooler in large-scale vessel	18
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	18
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	18
Shielding integral experiments of a bismuth sphere under D-T and D-D neutron sources with data-library validation	18
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	18
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	18
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	18
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	18
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	18
Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix	18
Implementation of ideal cascade model for uranium enrichment to nuclear fuel cycle simulator	18
A novel method for calculating annular fuel cell resonance effective temperature	18
Performance evaluation of a high flow rate annular linear induction pump using a simple equivalent circuit model taking into account dynamic end effects	18
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	17
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	17
Machine learning for analysis of real nuclear plant data in the frequency domain	17
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	17
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	17
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	17
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	17
The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	17
A pile noise experiment in the reference core of the nuclear research reactor LR-0	17
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	17
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	17
PCM-based uncertainty reduction in support of model validation for depletion calculations	17
Unmoderated molten salt reactors design optimisation for power stability	17
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	17
Many-objective rapid optimization of reactor shielding design based on NSGA - III	17
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	17
Research on TOPSIS multi-indicator evaluation model based on entropy weight method for C2N site selection	17
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	17
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	17
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	17
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	17
Machine-learned force fields for thermal neutron scattering law evaluations	16
Editorial Board	16
Conceptual design of the double tube burnable poison for the next generation small modular reactor	16
Comsol-based nuclear-thermal coupling methodology and its application in microreactors	16
NeuroSecure: Revolutionizing security in radioactive material transport with Deep Q-Learning and autonomous vehicle rerouting	16

Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	16
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	16
KARATE-1200: An enhanced neutron transport code for VVER-1200 reactor physics calculations	16
Layered target design method for global spectrum optimization of radioisotope production	16
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	16
Application of data-driven modeling and calibration methods in nuclear power plant prognosis digital twins	16
Comprehensive safety analysis of anticipated transient without scram in an integrated marine reactor	16
Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	16
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	16
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	16
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	16
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	16
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	15
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	15
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	15
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
A comprehensive GIS-driven hybrid approach for safe and sustainable radioactive waste disposal facility planning	15
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	15
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	15
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	15
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	15
Dynamic simulation of core power control for SPWR based on dynamic model bank	15
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	15
Hydraulic stability and energy loss mechanism in main feedwater pumps of the conventional island	15
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	15
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	15
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	15
J.M. Seiler’s major contributions to the understanding and modeling of corium – ceramic and concrete interactions	15
ALFRED reactor and hybrid systems: A test case	15
Development of a heat transfer model for the film boiling regime in a fouling layer	15
Evaluation of reflector design of ALLEGRO refractory core	15
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	15
Lightweight real-time sensor signal reconstruction in nuclear reactors via knowledge distillation and MBSNet	15
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	15
Experimental study on flow-induced vibration of single rod in axial flow	15
Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE	15
Editorial Board	15
Development of transport solver based on Hybrid Finite Element Method in Griffin	14
Space self-adaption global variance Reduction(SsGVR) method for large-scale radiation shielding calculation	14
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	14
Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses	14
Simulation of severe accidents in sodium-cooled fast reactors using ASTRA code with a molten clad motion model	14
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	14
Simulation and experimental verification for Rh-SPND burnup effect	14
Verification of multi-scale coupling program for high temperature gas-cooled reactor based on metamorphic testing	14
Decay heat analysis for advanced reactor spent fuel transportation and storage applications	14
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	14
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity	14
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer	14
Design and analysis of a direct reactor auxiliary cooling system for a pool-type small modular lead-based reactor	14
Comparative analysis of CANDU severe accident using CAISER	14
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics	14
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes	14
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	14
Performance evaluation of thermal conductivity models for fission gases with application to	14
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	14
Superiority of clay composite materials of bentonite intercalated with the bimetallic MOFs-Pb/Cu, and nano magnetite to enhance the gamma and neutron radiation shielding	14
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	14
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	14
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	14
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification	14
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au	14
Modeling and multifactor coupling sensitivity analysis of butterfly check valve under the station blackout of PWR	14
Derivation of operating conditions for the Jordan cement solidification process and evaluation of disposability of the cement waste form produced in the process	14
Dynamic response of a freely rotating butterfly valve in the advanced test reactor − dynamic coefficients modeling	14
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	14
Evaluation of tantalum–tungsten–oxygen compounds as lead-free radiation shielding materials	14
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	14
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	14
Noise characteristics and control of regulator spray valve: A hybrid computational and machine learning approach	14
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	14
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	14
Research on the influence law of submerged depth and flow rate of diversion canal on free surface vortex in coastal nuclear power plant	13
Efficient critical safety analysis model for PWR fuel assembly under transport accidents by neutron worth iteration	13
A finite element approach for nonlinear, transient heat conduction problems with convection, radiation or contact boundary conditions	13
Feasibility of Low-Enriched Uranium Fueled Nuclear Thermal Propulsion in the Low-Thrust Region Below 16klbf	13
Monte Carlo coupled Multi-Physics with spatially continuous material properties	13
Investigation on cross flow characteristics in a 5 × 5 rod bundle with a bowed central rod based on PIV quantification	13
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor	13
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions	13
PLEIADES: A numerical framework dedicated to the multiphysics and multiscale nuclear fuel behavior simulation	13
Reinvestigating the off-grid project priorities of small-scale nuclear reactors using an enhanced integrated fuzzy decision support system	13
Radiation damage analysis of the first generation VVER spent nuclear fuel casks	13
Study on reduction of pressure oscillation in low-velocity steam jet condensation	13
Thermo-hydrodynamics of multiple drops impinging simultaneously on the grooved tubular surface and smooth cylindrical surface with different wettabilities	13
Multiphysics and multi-scale design and analysis of nuclear thermal propulsion pellet bed reactor based on spherical cermet fuel element	13
Analysis of swarm flow and bubble residence time under pool scrubbing conditions	13
Multiscale numerical research on nucleate boiling enhancement from microscale to nanoscale	13
Analysis of thermal conductivity degradation in irradiated molybdenum for the safety and design of megawatt-class heat pipe reactors	13
Corrigendum to “Neutronic analysis for withdrawal of TRIGA MARK II reactor control rods using OpenMC program” [Ann. Nucl. Energy 217 (2025) 111330]	13
PSA level 1 analysis by considering redundancy and diversity of emergency diesel generators for APR-1400	13
Analysis of heat threshold in contact melting process	13
Results of the SSM-SICOPS melt tests of the EU-SAFEST project	13
System design and operation optimization on the hybrid system with nuclear power, concentrated solar, and thermal storage	13