Annals of Nuclear Energy

Article	Citations
Editorial Board	301
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	82
Radiation survey for Taiwan research reactor vessel	76
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
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	64
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	63
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	57
Development of lumped-parameter models for debris bed remelting analysis	46
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	45
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	45
The measurement of the 86Kr(n,2n)85mKr reaction cross section for the d-T neutrons	44
Neutron transmission measurements for silica glass at the KURNS-LINAC	44
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	43
A molten salt test loop for component and instrumentation testing	42
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	42
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	42
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	41
Verification of depletion capability of OpenMC using VERA depletion benchmark	41
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	40
Experimental investigation on sodium leak behaviour through a pinhole	39
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	38
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	37
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	36
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	36

Editorial Board	36
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	36
Editorial Board	35
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	35
Modelling of the expansion phase of Sodium fast reactor severe accident	35
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	34
Development and verification of the hexagonal core simulation capability of the NECP-X code	34
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	34
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	33
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	32
An analytic approach to the design of passively safe lead-cooled reactors	31
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	30
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	29
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	28
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	27
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	27
Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	27
Research on sensor fault tolerance technology in nuclear power plant control system	27
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	27
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	27
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	27
Dynamic mode decomposition for subcriticality measurement using measured data at single location	26
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	26
A compact Double-spiral electromagnetic pump for liquid metal cooling	26
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	25
Effects of two-dimensional hills combination with distance variation on the aerosols dispersion based on wind tunnel experiment	25
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	25
Impact of deposition morphology on critical heat flux during pool boiling from horizontal tubes	25
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	25
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	24
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	24
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	24
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	23
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	23
Investigation of environmental effects from the operation of a nuclear power plant	23
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	23
Variable universe fuzzy control of once-through steam generator feedwater	23
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	23
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	23
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	23
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	23
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	23
Mapping radioactive environments by use of sparse Gaussian processes regression	22
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	22
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	22
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	22
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	22
Development of a decommissioning waste assessment module for heavy water reactors	22
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	22
Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC	21

Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	21
A deep-learning representation of multi-group cross sections in lattice calculations	21
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	21
Neutron transmission measurement of thick n	21
The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	21
CFD simulation and wind tunnel investigation of atmospheric radionuclide dispersion around a nuclear power plant	21
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	21
A pile noise experiment in the reference core of the nuclear research reactor LR-0	20
Experimental and numerical study of an innovative twined tube HX design	20
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	20
Case study of flow instabilities in subchannels via multidimensional CFD approach	20
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	20
Development of a diffusive simplified double P20
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	20
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	20
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	20
Research on TOPSIS multi-indicator evaluation model based on entropy weight method for C2N site selection	20
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	19
Free convective condensation in the presence of noncondensable gases − A review with heat transfer studies	19
Analysis and enhancements of the coolant velocity estimation method in PWR core	19
CFD analysis on the safety performance of CSNS solid target under a postulated large loss of coolant accident	19
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	19
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	19
Editorial Board	19
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	19
Special issue: “In honour of the cowboy who has been riding the wide prairies of neutron transport for more than fifty years”	18
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	18
Characterization of plutonium for nuclear forensics using machine learning techniques	18
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	18
Editorial Board	18
Editorial Board	18
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	18
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	18
χ-18
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	18
Editorial Board	18
Criticality safety of fuel assemblies with missing fuel rods	18
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	18
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	18
An improved spatial-dependent model of neutron multiplicity counting for large-volume plutonium solution	18
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	18
Editorial Board	18
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	17
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	17
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	17
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	17
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	17
Many-objective rapid optimization of reactor shielding design based on NSGA - III	17
A simulation study on the thermal stratification characteristics induced by natural convection produced by cooler in large-scale vessel	17
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	17
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	17
A novel method for calculating annular fuel cell resonance effective temperature	17
Machine learning for analysis of real nuclear plant data in the frequency domain	17
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	17
Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix	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
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	17
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	17
Wavelet-based angular discretization finite difference method for neutron transport equation solving	17
A study on friction factor correlation considering the torsion effect in helical pipe flow	17
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	17
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	16
Development of a heat transfer model for the film boiling regime in a fouling layer	16
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	16
Unmoderated molten salt reactors design optimisation for power stability	16
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	16
Application of data-driven modeling and calibration methods in nuclear power plant prognosis digital twins	16
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	16
Noise characteristics and control of regulator spray valve: A hybrid computational and machine learning approach	16
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	16
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor	16
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	16
KARATE-1200: An enhanced neutron transport code for VVER-1200 reactor physics calculations	16
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	16
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	16
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	16
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	16
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	16
NeuroSecure: Revolutionizing security in radioactive material transport with Deep Q-Learning and autonomous vehicle rerouting	16
Verification of multi-scale coupling program for high temperature gas-cooled reactor based on metamorphic testing	15

Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	15
Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE	15
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	15
Lightweight real-time sensor signal reconstruction in nuclear reactors via knowledge distillation and MBSNet	15
Conceptual design of the double tube burnable poison for the next generation small modular reactor	15
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	15
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	15
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	15
A comprehensive GIS-driven hybrid approach for safe and sustainable radioactive waste disposal facility planning	15
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	15
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	15
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	15
Simulation and experimental verification for Rh-SPND burnup effect	15
Dynamic simulation of core power control for SPWR based on dynamic model bank	15
PCM-based uncertainty reduction in support of model validation for depletion calculations	15
Editorial Board	15
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	15
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	15
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	15
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	15
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	15
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	15
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	15
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	14
Hydraulic stability and energy loss mechanism in main feedwater pumps of the conventional island	14
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	14
Decay heat analysis for advanced reactor spent fuel transportation and storage applications	14
Experimental study on flow-induced vibration of single rod in axial flow	14
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	14
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	14
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	14
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	14
Evaluation of reflector design of ALLEGRO refractory core	14
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	14
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	14
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	14
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	14
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	14
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	14
Machine-learned force fields for thermal neutron scattering law evaluations	14
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity	14
Research on the influence law of submerged depth and flow rate of diversion canal on free surface vortex in coastal nuclear power plant	14
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	14
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	14
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	14
ALFRED reactor and hybrid systems: A test case	14
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	14
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	14
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	14
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	14
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	14
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	14
Method of characteristics with a new Macro-track transport acceleration for complex general geometry	14
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	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
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	14
Layered target design method for global spectrum optimization of radioisotope production	14
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	14
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
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes	13
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	13
Investigation of fission products distribution effected by spray system in PWR containment during severe accidents	13
Design and analysis of a direct reactor auxiliary cooling system for a pool-type small modular lead-based reactor	13
Analysis of swarm flow and bubble residence time under pool scrubbing conditions	13
The path-planning in radioactive environment based on HIOSD-PRM method	13
System design and operation optimization on the hybrid system with nuclear power, concentrated solar, and thermal storage	13
Investigation on cross flow characteristics in a 5 × 5 rod bundle with a bowed central rod based on PIV quantification	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
Dynamic response of a freely rotating butterfly valve in the advanced test reactor − dynamic coefficients modeling	13
Comparative analysis of CANDU severe accident using CAISER	13
Space self-adaption global variance Reduction(SsGVR) method for large-scale radiation shielding calculation	13
Machine learning prediction for thermal–hydraulic parameters of semicircular-fin fuel bundle in lead–bismuth fast reactor	13
Analysis of heat threshold in contact melting process	13
Remote dismantling system using a digital manufacturing system and workpiece localization for nuclear facility decommissioning	13
Atmospheric 137Cs dispersion following the Fukushima Daiichi nuclear accident: Local-scale simulations using CALMET and LAPMOD	13
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics	13
Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses	13
Simulation of severe accidents in sodium-cooled fast reactors using ASTRA code with a molten clad motion model	13
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer	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
Preliminary exploration of liquid metals turbulent heat flux model based on OpenFOAM solver: Second-order differential heat flux model	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
PLEIADES: A numerical framework dedicated to the multiphysics and multiscale nuclear fuel behavior simulation	12
PSA level 1 analysis by considering redundancy and diversity of emergency diesel generators for APR-1400	12
The impact of refueling schemes on the proliferation resistance of a pebble bed reactor	12
A novel method of neptunium-237 detection in its separated form and advanced fuel based on photonuclear reactions	12
Numerical investigation on effects of fuel rod with the position of bow deformation on the flow and heat transfer of PWR	12
Study on reduction of pressure oscillation in low-velocity steam jet condensation	12
Experimental study on 100 hour-term performance of high-temperature sodium heat pipes	12
Feasibility of americium detection and verification based on photonuclear reactions	12
Feasibility of Low-Enriched Uranium Fueled Nuclear Thermal Propulsion in the Low-Thrust Region Below 16klbf	12