Annals of Nuclear Energy

Article	Citations
Editorial Board	224
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	133
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	67
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	60
Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	58
Radiation survey for Taiwan research reactor vessel	55
Impact of experimental effects on a resolved resonance evaluation for practical applications	53
Editorial Board	52
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	49
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	44
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	43
Variable universe fuzzy control of once-through steam generator feedwater	42
Development of lumped-parameter models for debris bed remelting analysis	42
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	41
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	40
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	38
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	38
A molten salt test loop for component and instrumentation testing	36
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	36
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	36
Verification of depletion capability of OpenMC using VERA depletion benchmark	36
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	35
An analytic approach to the design of passively safe lead-cooled reactors	34
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	33
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	32

Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	32
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	31
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	31
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	30
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	30
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	30
Research on sensor fault tolerance technology in nuclear power plant control system	30
Mapping radioactive environments by use of sparse Gaussian processes regression	29
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	29
Neutron transmission measurements for silica glass at the KURNS-LINAC	27
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	27
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	27
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	27
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	27
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	27
Modelling of the expansion phase of Sodium fast reactor severe accident	26
Dynamic mode decomposition for subcriticality measurement using measured data at single location	26
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	25
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	25
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	25
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	24
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	24
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	24
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	24
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	24
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	24
The gamma deposition matrix method for gamma heating calculations for LWRs	24
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	23
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	23
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	23
Editorial Board	22
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	22
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	22
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	22
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	21
Development and verification of the hexagonal core simulation capability of the NECP-X code	21
Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary	21
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	21
A compact Double-spiral electromagnetic pump for liquid metal cooling	21
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	21
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	21
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems	21
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	21
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	21
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	21
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	21
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	21
Neutron transmission measurement of thick n	20
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	20
Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	20

Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix	20
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	20
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	20
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	20
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor	20
Experimental investigation on sodium leak behaviour through a pinhole	20
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	20
Development of a decommissioning waste assessment module for heavy water reactors	20
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	19
Development of a diffusive simplified double P19
Editorial Board	19
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	19
Numerical simulation of the molten pool stratification using moving particle simulation method	19
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	19
A study on friction factor correlation considering the torsion effect in helical pipe flow	19
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	19
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	19
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	19
Editorial Board	19
The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	19
Editorial Board	18
Analysis and enhancements of the coolant velocity estimation method in PWR core	18
Editorial Board	18
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	18
A novel method for calculating annular fuel cell resonance effective temperature	18
Criticality safety of fuel assemblies with missing fuel rods	18
χ-18
Estimation of reactor core water level using gamma distribution measured at multiple axial points outside reactor in severe accident scenarios employing interacting multiple model	18
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	18
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	18
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	18
Editorial Board	18
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	18
Numerical analysis for FP speciation in VERDON-2 experiment: Chemical re-vaporization of iodine in air ingress condition	18
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	18
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	17
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	17
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	17
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	17
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	17
Wavelet-based angular discretization finite difference method for neutron transport equation solving	17
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	17
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	17
Assessing and improving model fitness in MOCABA data assimilation	17
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	17
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	17
A pile noise experiment in the reference core of the nuclear research reactor LR-0	16
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	16
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	16
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	16
Selection methodology of the optimal cutting technology for dismantling of components in nuclear power plants	16
Unmoderated molten salt reactors design optimisation for power stability	16
Machine learning for analysis of real nuclear plant data in the frequency domain	16
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	16
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	16
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor	16
Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC	16
An insight into the flow field characteristics of the high temperature liquid Sodium (Na) with cavitation effects in the 600 MW fast reactor system	16
Performance evaluation of a high flow rate annular linear induction pump using a simple equivalent circuit model taking into account dynamic end effects	16
A deep-learning representation of multi-group cross sections in lattice calculations	16
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	16
Research on TOPSIS multi-indicator evaluation model based on entropy weight method for C2N site selection	16
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	16
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	15
Case study of flow instabilities in subchannels via multidimensional CFD approach	15
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	15
Many-objective rapid optimization of reactor shielding design based on NSGA - III	15
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	15
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	15
Evaluation of reflector design of ALLEGRO refractory core	15
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	15
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	15
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	15
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	15
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	15
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	15
Experimental and numerical study of an innovative twined tube HX design	15
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	15

Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	15
Characterization of plutonium for nuclear forensics using machine learning techniques	15
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	15
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	15
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	15
Stress analysis of shrink fitting process of ultra-thin reactor coolant pump rotor-can	14
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	14
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	14
Conceptual design of the double tube burnable poison for the next generation small modular reactor	14
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	14
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	14
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	14
Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation	14
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	14
Comparative study of meta-heuristic algorithms for reactor fuel reloading optimization based on the developed BP-ANN calculation method	14
Editorial Board	14
Risk analysis virtual ENvironment for dynamic event tree-based analyses	14
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	14
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	14
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	14
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	14
On the use of average power in predicting radioisotope productions	14
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	14
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	14
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	14
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	14
Neutronic performance optimization of reconfigured TRIGA cores	14
Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	14
PCM-based uncertainty reduction in support of model validation for depletion calculations	14
Development of NPP decommissioning cost estimation algorithm based on the CANDU structure	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
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	14
ALFRED reactor and hybrid systems: A test case	14
Transfer function modeling and simulation of HPR1000	14
Monte Carlo simulations of the water draining experimentof Giacint critical assembly	14
Development of a cyberattack response planning method for nuclear power plants by using the Markov decision process model	13
Experimental study on flow-induced vibration of single rod in axial flow	13
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	13
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	13
Machine-learned force fields for thermal neutron scattering law evaluations	13
Layered target design method for global spectrum optimization of radioisotope production	13
Simulation and experimental verification for Rh-SPND burnup effect	13
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	13
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	13
Development of a heat transfer model for the film boiling regime in a fouling layer	13
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	13
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	13
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	13
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	13
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	13
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	13
Transformation of classical PSA and DSA into the form of conditional event tree: An approach of human action in time dependent core damage risk	13
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	13
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	13
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	13
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	13
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	13
Dynamic simulation of core power control for SPWR based on dynamic model bank	13
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	13
On excess reactivity control of the advanced high temperature reactor (AHTR)	12
Cascade control system design for a space nuclear reactor	12
Multiphysics and multi-scale design and analysis of nuclear thermal propulsion pellet bed reactor based on spherical cermet fuel element	12
Measurement of the neutron and gamma spectra at the training and research reactor AKR-2	12
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity	12
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au	12
Development of transport solver based on Hybrid Finite Element Method in Griffin	12
Experimental study on 100 hour-term performance of high-temperature sodium heat pipes	12
Monte Carlo coupled Multi-Physics with spatially continuous material properties	12
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	12
Numerical investigation on effects of fuel rod with the position of bow deformation on the flow and heat transfer of PWR	12
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	12
PLEIADES: A numerical framework dedicated to the multiphysics and multiscale nuclear fuel behavior simulation	12
Adaptive learning observer based fixed-time stable controller for load following of a Pressurized Water Reactor	12
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	12
Research on the influence law of submerged depth and flow rate of diversion canal on free surface vortex in coastal nuclear power plant	12
A mathematical approach to using the forgetting curve to evaluate experience and training factors in human reliability analysis	12
Results of the SSM-SICOPS melt tests of the EU-SAFEST project	12
Design of open-tank-in-pool-type educational critical assemblies using UO2 and U-7Mo fuels	12
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	12
A preliminary study on the blistering behavior of dispersion plate-type fuel assembly	12
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer	12
3-D gamma radiation field reconstruction method using limited measurements for multiple radioactive sources	12
Application of different Krylov subspace methods in subcooled flow boiling simulation	12
Sensitivity analysis of internal flow distribution in the Tsinghua high flux reactor	12
Optimal rule based fuzzy-PI controller for core power control of nuclear reactor	12
Preliminary exploration of liquid metals turbulent heat flux model based on OpenFOAM solver: Second-order differential heat flux model	12
Research on application of heterogeneous resonance Integral for double heterogeneous system	12
Investigation of Natural Helium Circulation Inside Dual Channels Prismatic Modular Reactor	12
Design and analysis of a direct reactor auxiliary cooling system for a pool-type small modular lead-based reactor	12
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	12
PSA level 1 analysis by considering redundancy and diversity of emergency diesel generators for APR-1400	12
Research and application of the neutronics and thermal–hydraulic coupling based on the MORE framework	12
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	11
Rapid neutronic and thermal hydraulic analysis of LEU space reactor core	11
Large-scale production by centrifugation of isotopically modified molybdenum for nuclear reactors and its cost evaluation	11