Annals of Nuclear Energy

Article	Citations
Editorial Board	83
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	77
Radiation survey for Taiwan research reactor vessel	69
Impact of experimental effects on a resolved resonance evaluation for practical applications	65
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	64
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	58
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	47
Neutron transmission measurements for silica glass at the KURNS-LINAC	46
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	45
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	44
A molten salt test loop for component and instrumentation testing	44
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	44
Verification of depletion capability of OpenMC using VERA depletion benchmark	43
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	43
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	43
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	42
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	41
Editorial Board	41
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	41
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	40
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	39
Modelling of the expansion phase of Sodium fast reactor severe accident	38
Editorial Board	38
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	38

Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	36
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	36
Development and verification of the hexagonal core simulation capability of the NECP-X code	36
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	35
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	35
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	34
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	34
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	33
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	32
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	31
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	30
Development and improvement of the quadratic depletion method	30
A compact Double-spiral electromagnetic pump for liquid metal cooling	30
Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	30
Dynamic mode decomposition for subcriticality measurement using measured data at single location	29
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	29
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	28
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	28
Effects of two-dimensional hills combination with distance variation on the aerosols dispersion based on wind tunnel experiment	28
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	27
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	27
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	27
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	26
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	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 calculation model for radionuclide dispersion in the ocean and its credibility evaluation	26
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	26
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	24
Research on sensor fault tolerance technology in nuclear power plant control system	24
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	24
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	24
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	24
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	24
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	24
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	24
Variable universe fuzzy control of once-through steam generator feedwater	23
Impact of deposition morphology on critical heat flux during pool boiling from horizontal tubes	23
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	23
Development of a decommissioning waste assessment module for heavy water reactors	23
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	23
Investigation of environmental effects from the operation of a nuclear power plant	23
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	23
Mapping radioactive environments by use of sparse Gaussian processes regression	23
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	22
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	22
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	22
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	22
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	21
Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	21

The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	21
Development of a diffusive simplified double P21
CFD simulation and wind tunnel investigation of atmospheric radionuclide dispersion around a nuclear power plant	21
A deep-learning representation of multi-group cross sections in lattice calculations	21
Experimental and numerical study of an innovative twined tube HX design	21
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	21
Neutron transmission measurement of thick n	21
Editorial Board	20
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	20
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	20
Case study of flow instabilities in subchannels via multidimensional CFD approach	20
Free convective condensation in the presence of noncondensable gases − A review with heat transfer studies	20
CFD analysis on the safety performance of CSNS solid target under a postulated large loss of coolant accident	20
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	20
A pile noise experiment in the reference core of the nuclear research reactor LR-0	20
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	19
Editorial Board	19
Editorial Board	19
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor	19
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	19
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	19
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	19
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	19
Machine learning for analysis of real nuclear plant data in the frequency domain	19
Analysis and enhancements of the coolant velocity estimation method in PWR core	19
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	18
Special issue: “In honour of the cowboy who has been riding the wide prairies of neutron transport for more than fifty years”	18
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	18
An improved spatial-dependent model of neutron multiplicity counting for large-volume plutonium solution	18
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	18
χ-18
Criticality safety of fuel assemblies with missing fuel rods	18
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	18
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	18
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	18
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	18
Editorial Board	18
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	18
Editorial Board	18
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	18
Characterization of plutonium for nuclear forensics using machine learning techniques	18
Many-objective rapid optimization of reactor shielding design based on NSGA - III	17
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	17
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	17
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	17
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	17
Wavelet-based angular discretization finite difference method for neutron transport equation solving	17
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	17
Research on TOPSIS multi-indicator evaluation model based on entropy weight method for C2N site selection	17
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	17
A novel method for calculating annular fuel cell resonance effective temperature	17
Performance evaluation of a high flow rate annular linear induction pump using a simple equivalent circuit model taking into account dynamic end effects	17
A simulation study on the thermal stratification characteristics induced by natural convection produced by cooler in large-scale vessel	17
A study on friction factor correlation considering the torsion effect in helical pipe flow	17
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	17
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	17
Unmoderated molten salt reactors design optimisation for power stability	17
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	17
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	17
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	17
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	17
Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix	17
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	16
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	16
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	16
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	16
Layered target design method for global spectrum optimization of radioisotope production	16
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	16
KARATE-1200: An enhanced neutron transport code for VVER-1200 reactor physics calculations	16
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	16
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	16
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	16
Editorial Board	16
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	16
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	16
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	16
PCM-based uncertainty reduction in support of model validation for depletion calculations	16
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	16
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	16
Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	16

Conceptual design of the double tube burnable poison for the next generation small modular reactor	16
Machine-learned force fields for thermal neutron scattering law evaluations	16
Simulation and experimental verification for Rh-SPND burnup effect	16
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	15
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	15
Evaluation of tantalum–tungsten–oxygen compounds as lead-free radiation shielding materials	15
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	15
Experimental study on flow-induced vibration of single rod in axial flow	15
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	15
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	15
NeuroSecure: Revolutionizing security in radioactive material transport with Deep Q-Learning and autonomous vehicle rerouting	15
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	15
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	15
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	15
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	15
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	15
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	15
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	15
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	15
Noise characteristics and control of regulator spray valve: A hybrid computational and machine learning approach	15
A comprehensive GIS-driven hybrid approach for safe and sustainable radioactive waste disposal facility planning	15
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
Decay heat analysis for advanced reactor spent fuel transportation and storage applications	15
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	15
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	15
Application of data-driven modeling and calibration methods in nuclear power plant prognosis digital twins	15
Statistical characterization of liquid film fluctuations during gas-liquid two-phase counter-current flow in a 1/30 scaled-down test facility of a pressurized water reactor (PWR) hot leg	15
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	14
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	14
Dynamic simulation of core power control for SPWR based on dynamic model bank	14
Dynamic response of a freely rotating butterfly valve in the advanced test reactor − dynamic coefficients modeling	14
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity	14
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	14
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	14
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	14
Evaluation of reflector design of ALLEGRO refractory core	14
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	14
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	14
Lightweight real-time sensor signal reconstruction in nuclear reactors via knowledge distillation and MBSNet	14
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	14
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	14
Simulation of severe accidents in sodium-cooled fast reactors using ASTRA code with a molten clad motion model	14
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	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
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	14
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	14
Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE	14
Hydraulic stability and energy loss mechanism in main feedwater pumps of the conventional island	14
Development of a heat transfer model for the film boiling regime in a fouling layer	14
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	14
ALFRED reactor and hybrid systems: A test case	14
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer	14
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	14
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	14
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	14
Verification of multi-scale coupling program for high temperature gas-cooled reactor based on metamorphic testing	14
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	14
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics	13
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes	13
Optimization method of fuel-reloading pattern for PWR based on the improved convolutional neural network and genetic algorithm	13
Adaptive learning observer based fixed-time stable controller for load following of a Pressurized Water Reactor	13
Analysis of bubble migration characteristics and design of mitigation measures after a steam generator tube rupture accident in a small lead-based reactor	13
A preliminary study on the blistering behavior of dispersion plate-type fuel assembly	13
Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element	13
The path-planning in radioactive environment based on HIOSD-PRM method	13
Rapid neutronic and thermal hydraulic analysis of LEU space reactor core	13
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification	13
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au	13
Modeling and multifactor coupling sensitivity analysis of butterfly check valve under the station blackout of PWR	13
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor	13
Space self-adaption global variance Reduction(SsGVR) method for large-scale radiation shielding calculation	13
Thermo-hydrodynamics of multiple drops impinging simultaneously on the grooved tubular surface and smooth cylindrical surface with different wettabilities	13
Method research and engineering validation of the improved homogenization for the heavy reflector in VVER	13
Damage performance analysis of prestressed concrete containments following a loss of coolant accident considering different external temperatures	13
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions	13
Research on application of heterogeneous resonance Integral for double heterogeneous system	13
On excess reactivity control of the advanced high temperature reactor (AHTR)	13
Investigation on cross flow characteristics in a 5 × 5 rod bundle with a bowed central rod based on PIV quantification	13
System design and operation optimization on the hybrid system with nuclear power, concentrated solar, and thermal storage	13
Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses	13
Performance evaluation of thermal conductivity models for fission gases with application to	13
Derivation of operating conditions for the Jordan cement solidification process and evaluation of disposability of the cement waste form produced in the process	13
Analysis of heat threshold in contact melting process	13
Analysis of swarm flow and bubble residence time under pool scrubbing conditions	13
In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment	13
Sensitivity analysis of internal flow distribution in the Tsinghua high flux reactor	13
Investigation of Natural Helium Circulation Inside Dual Channels Prismatic Modular Reactor	13
Design and analysis of a direct reactor auxiliary cooling system for a pool-type small modular lead-based reactor	13
Results of the SSM-SICOPS melt tests of the EU-SAFEST project	13
Corrigendum to “Neutronic analysis for withdrawal of TRIGA MARK II reactor control rods using OpenMC program” [Ann. Nucl. Energy 217 (2025) 111330]	13
Monte Carlo coupled Multi-Physics with spatially continuous material properties	13
Development of transport solver based on Hybrid Finite Element Method in Griffin	13
Comparative analysis of CANDU severe accident using CAISER	13
Experimental and numerical study on the transient heat transfer process for fluoride salt-to-air cooler	12