Annals of Nuclear Energy

Article	Citations
Editorial Board	251
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	137
Radiation survey for Taiwan research reactor vessel	71
Impact of experimental effects on a resolved resonance evaluation for practical applications	68
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	59
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	58
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	57
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	56
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	54
Experimental investigation on sodium leak behaviour through a pinhole	44
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	44
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	43
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	42
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	42
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	40
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	39
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	39
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	38
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	38
Research on sensor fault tolerance technology in nuclear power plant control system	38
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	37
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	36
Numerical analysis on steam–air condensation at low wall sub-cooling under natural convection	35
Development of lumped-parameter models for debris bed remelting analysis	35
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	35

Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	34
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	33
Neutron transmission measurements for silica glass at the KURNS-LINAC	32
Mapping radioactive environments by use of sparse Gaussian processes regression	31
Verification of depletion capability of OpenMC using VERA depletion benchmark	31
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	31
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	31
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	31
The gamma deposition matrix method for gamma heating calculations for LWRs	30
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	30
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	30
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	29
Editorial Board	28
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	27
Dynamic mode decomposition for subcriticality measurement using measured data at single location	27
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	27
Modelling of the expansion phase of Sodium fast reactor severe accident	27
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	26
Development and verification of the hexagonal core simulation capability of the NECP-X code	26
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	26
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	26
A compact Double-spiral electromagnetic pump for liquid metal cooling	25
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	25
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	25
Editorial Board	24
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	24
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	24
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	24
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	23
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	23
An analytic approach to the design of passively safe lead-cooled reactors	23
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	23
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	23
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	22
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	22
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	22
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	22
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	22
Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	22
Investigation of environmental effects from the operation of a nuclear power plant	22
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	22
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	22
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	22
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	22
Development of a decommissioning waste assessment module for heavy water reactors	21
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	21
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	21
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	21
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	21
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	21

Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	21
Development of a diffusive simplified double P21
A molten salt test loop for component and instrumentation testing	21
Variable universe fuzzy control of once-through steam generator feedwater	21
Editorial Board	20
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	20
Editorial Board	20
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	20
Estimation of reactor core water level using gamma distribution measured at multiple axial points outside reactor in severe accident scenarios employing interacting multiple model	20
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	20
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	20
Characterization of plutonium for nuclear forensics using machine learning techniques	20
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	20
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	20
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	20
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor	20
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	20
Editorial Board	20
Editorial Board	19
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	19
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	19
Criticality safety of fuel assemblies with missing fuel rods	19
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	19
A novel method for calculating annular fuel cell resonance effective temperature	19
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	19
Analysis and enhancements of the coolant velocity estimation method in PWR core	19
Editorial Board	19
A pile noise experiment in the reference core of the nuclear research reactor LR-0	18
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	18
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	18
CFD analysis on the safety performance of CSNS solid target under a postulated large loss of coolant accident	18
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	18
Case study of flow instabilities in subchannels via multidimensional CFD approach	18
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	18
Wavelet-based angular discretization finite difference method for neutron transport equation solving	18
Selection methodology of the optimal cutting technology for dismantling of components in nuclear power plants	18
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	18
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	18
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	17
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	17
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	17
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	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
Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix	17
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	17
A study on friction factor correlation considering the torsion effect in helical pipe flow	17
Research on TOPSIS multi-indicator evaluation model based on entropy weight method for C2N site selection	17
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor	17
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	17
Unmoderated molten salt reactors design optimisation for power stability	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
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	16
Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC	16
χ-16
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	16
Neutron transmission measurement of thick n	16
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	16
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	16
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	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
The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	16
Machine learning for analysis of real nuclear plant data in the frequency domain	16
Experimental and numerical study of an innovative twined tube HX design	16
A deep-learning representation of multi-group cross sections in lattice calculations	16
Many-objective rapid optimization of reactor shielding design based on NSGA - III	16
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	16
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	16
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	16
Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	16
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	16
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	16
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	16
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	15
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	15
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	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
Conceptual design of the double tube burnable poison for the next generation small modular reactor	15

A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	15
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	15
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	15
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	15
PCM-based uncertainty reduction in support of model validation for depletion calculations	15
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	15
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	15
KARATE-1200: An enhanced neutron transport code for VVER-1200 reactor physics calculations	15
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	15
Evaluation of reflector design of ALLEGRO refractory core	15
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	15
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	15
Machine-learned force fields for thermal neutron scattering law evaluations	15
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	15
Layered target design method for global spectrum optimization of radioisotope production	15
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	15
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	15
On the use of average power in predicting radioisotope productions	14
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	14
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	14
Experimental study on flow-induced vibration of single rod in axial flow	14
Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation	14
Development of NPP decommissioning cost estimation algorithm based on the CANDU structure	14
Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	14
Development of a cyberattack response planning method for nuclear power plants by using the Markov decision process model	14
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	14
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	14
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	14
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	14
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	14
Editorial Board	14
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	14
Dynamic simulation of core power control for SPWR based on dynamic model bank	14
Development of a heat transfer model for the film boiling regime in a fouling layer	13
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	13
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	13
ALFRED reactor and hybrid systems: A test case	13
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	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
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	13
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	13
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	13
Lightweight real-time sensor signal reconstruction in nuclear reactors via knowledge distillation and MBSNet	13
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	13
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	13
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	13
A comprehensive GIS-driven hybrid approach for safe and sustainable radioactive waste disposal facility planning	13
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	13
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	13
Risk analysis virtual ENvironment for dynamic event tree-based analyses	13
PSA level 1 analysis by considering redundancy and diversity of emergency diesel generators for APR-1400	13
Transfer function modeling and simulation of HPR1000	13
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	13
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	13
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	13
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	13
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	13
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	13
Simulation and experimental verification for Rh-SPND burnup effect	13
Hydraulic stability and energy loss mechanism in main feedwater pumps of the conventional island	13
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	13
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	13
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	13
Comparative study of meta-heuristic algorithms for reactor fuel reloading optimization based on the developed BP-ANN calculation method	13
Dynamic response of a freely rotating butterfly valve in the advanced test reactor − dynamic coefficients modeling	12
Machine learning prediction for thermal–hydraulic parameters of semicircular-fin fuel bundle in lead–bismuth fast reactor	12
Dimensionality reduction combined with particle swarm optimization algorithm for solving high-dimensional nuclear data target accuracy evaluation problem	12
Research and application of the neutronics and thermal–hydraulic coupling based on the MORE framework	12
Remote dismantling system using a digital manufacturing system and workpiece localization for nuclear facility decommissioning	12
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes	12
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics	12
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor	12
Feasibility of Low-Enriched Uranium Fueled Nuclear Thermal Propulsion in the Low-Thrust Region Below 16klbf	12
Investigation of fission products distribution effected by spray system in PWR containment during severe accidents	12
Effects of additives on the thermal stability of silver tellurite glass system	12
Sensitivity analysis of internal flow distribution in the Tsinghua high flux reactor	12
A mathematical approach to using the forgetting curve to evaluate experience and training factors in human reliability analysis	12
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	12
Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor	12
Application of different Krylov subspace methods in subcooled flow boiling simulation	12
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions	12
Nitrogen containing reductants for the corrosion control of alloys relevant to nuclear reactors	12
Application of GS	12
Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses	12
Derivation of operating conditions for the Jordan cement solidification process and evaluation of disposability of the cement waste form produced in the process	12
Activated sodium adjuster rod design for enhanced delayed-photoneutron yield in heavy water reactors	12
Damage performance analysis of prestressed concrete containments following a loss of coolant accident considering different external temperatures	12
Characterization of neutron spectrum at the neutron radiography of RSG-GAS reactor using a passive single-cylindrical neutron spectrometer	12
Designing a combined guide and investigating the role of collimator in neutron intensity uniformity	12
A preliminary study on the blistering behavior of dispersion plate-type fuel assembly	12
Method research and engineering validation of the improved homogenization for the heavy reflector in VVER	12
Performance evaluation of thermal conductivity models for fission gases with application to	12
Thermo-hydrodynamics of multiple drops impinging simultaneously on the grooved tubular surface and smooth cylindrical surface with different wettabilities	12
Experimental and numerical study on the transient heat transfer process for fluoride salt-to-air cooler	12
Development of a new control rod drive mechanism design for the ISU AGN-201M reactor	12