Annals of Nuclear Energy

Article	Citations
Modelling of the expansion phase of Sodium fast reactor severe accident	197
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	126
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	68
Impact of experimental effects on a resolved resonance evaluation for practical applications	58
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	58
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	57
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	56
The gamma deposition matrix method for gamma heating calculations for LWRs	51
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	50
Editorial Board	49
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	48
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	47
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	43
Editorial Board	42
Radiation survey for Taiwan research reactor vessel	41
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	40
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	40
Development of lumped-parameter models for debris bed remelting analysis	38
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	38
Benchmarking a point reactor kinetics method with delayed neutron precursors transport using data from molten salt reactor experiment	37
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	36
Development and verification of the hexagonal core simulation capability of the NECP-X code	36
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	36
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	35
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	35

Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel	34
Verification of depletion capability of OpenMC using VERA depletion benchmark	34
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	34
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	33
Barium-calcium-lead-borate glasses: A new extent optimization of gamma-ray shielding	32
Development and validation of NECP-SARAX: An advanced neutron analysis code system for accelerator-driven subcritical systems	32
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	32
Experimental investigation on sodium leak behaviour through a pinhole	31
Dynamic mode decomposition for subcriticality measurement using measured data at single location	30
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	30
Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary	30
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	30
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	29
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	29
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	28
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	28
A compact Double-spiral electromagnetic pump for liquid metal cooling	28
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	27
Parametric investigation of mercury cell electrolysis for isotopic separation of Li using coupled numerical methods	27
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	26
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	26
A molten salt test loop for component and instrumentation testing	25
A semi-implicit Chord Length Sampling method for dispersion fuel analysis	25
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	25
Mapping radioactive environments by use of sparse Gaussian processes regression	25
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process	25
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	24
Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation	24
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	24
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	24
An analytic approach to the design of passively safe lead-cooled reactors	23
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	23
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems	23
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	23
Neutron transmission measurements for silica glass at the KURNS-LINAC	23
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	23
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	23
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	22
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	22
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	22
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	22
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	22
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	22
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	22
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	21
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	21
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	21
Variable universe fuzzy control of once-through steam generator feedwater	21
Research on sensor fault tolerance technology in nuclear power plant control system	21
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	21

Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	21
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	20
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	20
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	20
Editorial Board	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
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	20
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	20
Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2	20
Numerical study on a wire-wrapped fuel rod vibration induced by axial Pb-Bi coolant flow	20
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	20
Development of a diffusive simplified double P19
Unmoderated molten salt reactors design optimisation for power stability	19
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	19
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	19
A pile noise experiment in the reference core of the nuclear research reactor LR-0	19
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	19
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	19
Development of a flow sweeping mixing model for helical fuel rod bundles	19
Treatment of molten fluoride salt-exposed graphite: Cleaning made simple	19
A novel method for calculating annular fuel cell resonance effective temperature	19
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	19
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	19
Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE	19
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
Wavelet-based angular discretization finite difference method for neutron transport equation solving	18
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	18
Characterization of plutonium for nuclear forensics using machine learning techniques	18
The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy	18
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	18
Editorial Board	18
Editorial Board	18
Neutron transmission measurement of thick n	18
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor	18
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	18
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	18
Numerical simulation of the molten pool stratification using moving particle simulation method	18
Editorial Board	17
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	17
Numerical analysis for FP speciation in VERDON-2 experiment: Chemical re-vaporization of iodine in air ingress condition	17
A study on friction factor correlation considering the torsion effect in helical pipe flow	17
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	17
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	17
Experimental and numerical study of an innovative twined tube HX design	17
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	17
A higher order implicit stair-tailored scheme for the modified Burgers’ equation	17
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	17
An insight into the flow field characteristics of the high temperature liquid Sodium (Na) with cavitation effects in the 600 MW fast reactor system	17
Analysis and enhancements of the coolant velocity estimation method in PWR core	17
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	17
Editorial Board	17
χ-16
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	16
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	16
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	16
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	16
Investigation of shielding and dosimetric parameters for neutrons emitted from various types of fission sources	16
Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes	16
Machine learning for analysis of real nuclear plant data in the frequency domain	16
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	16
Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	16
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	16
A numerical investigation on the heat transfer and turbulence production characteristics induced by a swirl spacer in a single-tube geometry under single-phase flow condition	16
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	16
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor	16
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	16
Development of a decommissioning waste assessment module for heavy water reactors	16
Assessing and improving model fitness in MOCABA data assimilation	16
Many-objective rapid optimization of reactor shielding design based on NSGA - III	16
Criticality safety of fuel assemblies with missing fuel rods	15
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	15
On the use of average power in predicting radioisotope productions	15
PCM-based uncertainty reduction in support of model validation for depletion calculations	15
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	15
A deep-learning representation of multi-group cross sections in lattice calculations	15
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	15
Performance evaluation of a high flow rate annular linear induction pump using a simple equivalent circuit model taking into account dynamic end effects	15
Research on energy group structure optimization method for pressure water reactor plate-type fuel based on particle swarm algorithm	15
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	15

Selection methodology of the optimal cutting technology for dismantling of components in nuclear power plants	15
Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC	15
Case study of flow instabilities in subchannels via multidimensional CFD approach	15
On the use of criticality and depletion benchmarks for verification of nuclear data	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	15
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	15
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	15
ALFRED reactor and hybrid systems: A test case	14
Development of a cyberattack response planning method for nuclear power plants by using the Markov decision process model	14
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment	14
Editorial Board	14
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	14
Monte Carlo simulations of the water draining experimentof Giacint critical assembly	14
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	14
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	14
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	14
Transformation of classical PSA and DSA into the form of conditional event tree: An approach of human action in time dependent core damage risk	14
Conceptual design of the double tube burnable poison for the next generation small modular reactor	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
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	14
Neutronic performance optimization of reconfigured TRIGA cores	14
Comparative study of meta-heuristic algorithms for reactor fuel reloading optimization based on the developed BP-ANN calculation method	14
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	14
Evaluation of reflector design of ALLEGRO refractory core	14
Stress analysis of shrink fitting process of ultra-thin reactor coolant pump rotor-can	14
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	14
Experimental study on flow-induced vibration of single rod in axial flow	14
Risk analysis virtual ENvironment for dynamic event tree-based analyses	14
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	14
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	14
In-situ demonstration of engineered barrier system (In-DEBS) at KURT: Coupled thermal-hydro-mechanical behavior of buffer	13
Machine-learned force fields for thermal neutron scattering law evaluations	13
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	13
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	13
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review	13
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	13
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	13
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	13
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	13
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	13
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	13
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	13
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	13
Mathematical modelling of bubble formation at top-submerged nozzles placed inside a quiescent liquid	13
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	13
Transfer function modeling and simulation of HPR1000	13
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	13
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	13
Simulation and experimental verification for Rh-SPND burnup effect	13
Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	13
Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation	13
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	13
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	13
Research on the effect of non-uniform inflow on head characteristics of reactor coolant pumps	13
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	13
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	13
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)	13
In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment	13
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	13
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	13
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	13
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	13
Development of a heat transfer model for the film boiling regime in a fouling layer	13
Dynamic simulation of core power control for SPWR based on dynamic model bank	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
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	13
Layered target design method for global spectrum optimization of radioisotope production	13
A novel method of neptunium-237 detection in its separated form and advanced fuel based on photonuclear reactions	12
Development of a new control rod drive mechanism design for the ISU AGN-201M reactor	12
Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element	12
Optimization method of fuel-reloading pattern for PWR based on the improved convolutional neural network and genetic algorithm	12
Simulation study of physical cryptographic verification of nuclear warheads based on NRF excited by LCS γ-ray source	12
Effects of additives on the thermal stability of silver tellurite glass system	12
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	12
Application of different Krylov subspace methods in subcooled flow boiling simulation	12
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification	12
Method of characteristics with a new Macro-track transport acceleration for complex general geometry	12
Numerical investigation on effects of fuel rod with the position of bow deformation on the flow and heat transfer of PWR	12
A new methodology to speed-up fuel lattice design optimization using decision trees and new objective functions	12
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package	12
Stress analysis of PWR pressurizer surge-line during single phase and two-phase thermal stratification	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
Method research and engineering validation of the improved homogenization for the heavy reflector in VVER	12
Rapid neutronic and thermal hydraulic analysis of LEU space reactor core	12
Adaptive learning observer based fixed-time stable controller for load following of a Pressurized Water Reactor	12
Experimental and numerical study on the transient heat transfer process for fluoride salt-to-air cooler	12
Monte Carlo analysis of BWR geometries using a cycle check-up methodology	12
On excess reactivity control of the advanced high temperature reactor (AHTR)	12
Application of GS	12
Quantum evolutionary algorithm based power optimization control strategy for China initiative accelerator driven subcritical system	12
Turbulent flow effect on integrity of pressurized RVIs	12
Evaluating the variations of point kinetics parameters in pressurized heavy water reactor analyses	12
Investigation of fission products distribution effected by spray system in PWR containment during severe accidents	12