Annals of Nuclear Energy

Article	Citations
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	154
A novel approach for software reliability analysis of digital instrumentation and control systems in nuclear power plants	117
Modelling of the expansion phase of Sodium fast reactor severe accident	64
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	55
Assessment of WWER 1000 core degradation in a severe accident condition induced by MB-LOCA	51
Development and verification of the hexagonal core simulation capability of the NECP-X code	50
Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code	47
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	44
Impact of experimental effects on a resolved resonance evaluation for practical applications	43
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	42
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	41
Innovative control mechanism for research and test reactors using mandrel-shaped control rods	41
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method	40
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	38
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	36
Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor	36
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	35
Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel	34
Monte Carlo sensitivity analyses of isothermal temperature coefficient in solid-moderated and solid-reflected cores at Kyoto University critical assembly	34
Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary	34
The gamma deposition matrix method for gamma heating calculations for LWRs	33
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	32
A molten salt test loop for component and instrumentation testing	31
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	30
Experimental investigation on sodium leak behaviour through a pinhole	30

Editorial Board	30
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	30
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	29
Application of risk informed safety margin characterization to the analysis of a pressurized water reactor	29
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	29
Editorial Board	29
Radiation survey for Taiwan research reactor vessel	29
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	29
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	29
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	28
Variable universe fuzzy control of once-through steam generator feedwater	28
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	27
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	27
Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles	26
Neutron transmission measurements for silica glass at the KURNS-LINAC	26
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	26
A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis	26
Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load	26
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	25
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	25
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	25
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	24
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	24
Dynamic mode decomposition for subcriticality measurement using measured data at single location	24
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	23
Climate resilience analysis of nuclear energy by big data associated with Internet of Things (IoT)	23
One dimensional analytical model considering end effects for analysis of electromagnetic pressure characteristics of annular linear induction electromagnetic pump	23
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	23
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	23
Corrigendum to ‘Integral transport in a three region sphere with associated benchmark problems’ [Ann. Nucl. Energy 32 (2005) 1047–1067]	23
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	23
Verification of depletion capability of OpenMC using VERA depletion benchmark	22
Research on sensor fault tolerance technology in nuclear power plant control system	22
Pressurizer dynamic model and emulated programmable logic controllers for nuclear power plants cybersecurity investigations	22
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	22
A compact Double-spiral electromagnetic pump for liquid metal cooling	22
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	22
Integral experiments in the VENUS-F reactor	21
New approach to find the equilibrium cycle in PWR reactors using genetic algorithms	21
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems	21
An analytic approach to the design of passively safe lead-cooled reactors	21
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	21
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	21
Mapping radioactive environments by use of sparse Gaussian processes regression	21
Editorial Board	20
Immobilization of iodine waste at low sintering temperature: Phase evolution and microstructure transformation	20
A novel method for calculating annular fuel cell resonance effective temperature	20
Unmoderated molten salt reactors design optimisation for power stability	20
Application of the Analytic Hierarchy Process in selecting long-term storage option for spent nuclear fuel in South Africa	20
A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions	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	19
A multi-level nonlinear elimination-based JFNK method for multi-scale multi-physics coupling problem in pebble-bed HTR	19
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD	19
Pressure control of Once-through steam generator using Proximal policy optimization algorithm	19
Estimation of reactor core water level using gamma distribution measured at multiple axial points outside reactor in severe accident scenarios employing interacting multiple model	19
A pile noise experiment in the reference core of the nuclear research reactor LR-0	19
Development of a diffusive simplified double P19
Fragility analysis and probabilistic safety evaluation of the nuclear containment structure under different prestressing loss conditions	19
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison	18
A new multi-scale coupling simulation of natural circulation system based on self-adaption data interaction method	18
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	18
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data	18
Application of Backward Differential Formula and Anderson’s method for multigroup diffusion transient equation	18
Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor	18
Erratum to “On integrating Monte Carlo calculations in and around near-critical configurations – I. Methodology” [Ann. Nucl. Energy 172 (2022) 109063]	18
Implementation and optimization of WDT algorithm on IMPC-Neutron and comparison of efficiency of various algorithms	18
Numerical analysis of transient heat and mass transfer for a water heat pipe under non-uniform heating conditions	18
Wavelet-based angular discretization finite difference method for neutron transport equation solving	18
Erratum to “Non-intrusive stochastic approach for nuclear cross-sections adjustment” [Ann. Nucl. Energy 155 (2021) 108162]	18
Species transport analysis of noble metal fission product transport, deposition, and extraction in the molten salt reactor experiment	18
Editorial Board	18
A deep-learning representation of multi-group cross sections in lattice calculations	18
On the use of criticality and depletion benchmarks for verification of nuclear data	18
Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors	18
Subcritical neutron noise measurements for plutonium systems with varying geometry and mass	18
Radial basis function neural network controller for power control of molten salt breeder reactor of nuclear power plant	18
The relationship between the backward and forward equations of stochastic neutron transport and associated matters	17
Numerical simulation of the molten pool stratification using moving particle simulation method	17
Verification of nuclear data libraries used to design molten salt blankets of a fusion neutron source	17
Editorial Board	17
Criticality safety of fuel assemblies with missing fuel rods	17
An experimental investigation on rewetting of a 54 pins fuel bundle under steam environment by radial jet injection	17
Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC	17
Assessing and improving model fitness in MOCABA data assimilation	17
Editorial Board	17
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor	17
Characterization of plutonium for nuclear forensics using machine learning techniques	17
χ-17
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS	16
Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature	16
Analysis and enhancements of the coolant velocity estimation method in PWR core	16
Development of a decommissioning waste assessment module for heavy water reactors	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
Selection methodology of the optimal cutting technology for dismantling of components in nuclear power plants	16
Numerical analysis for FP speciation in VERDON-2 experiment: Chemical re-vaporization of iodine in air ingress condition	16
Mathematical foundations of the three-dimensional neutron hydrodynamics coupled transport equations	16
Experimental and numerical study of an innovative twined tube HX design	16
Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs	16
Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant	16
High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties	15
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes	15
Multi-objective optimization method for reactor shielding design based on SMS-EMOA	15
Research on decay heat removal effectiveness in pool-type fast reactor CEFR based on system code SAC-DRACS coupled with CFD software	15
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code	15
Case study of flow instabilities in subchannels via multidimensional CFD approach	15
Best-practice severe accident uncertainty and sensitivity analysis for a short-term SBO sequence of a reference PWR using MAAP5	15
Machine learning for analysis of real nuclear plant data in the frequency domain	15
Many-objective rapid optimization of reactor shielding design based on NSGA - III	15
Numerical investigation on heat transfer characteristics of liquid metal cross flow over tube bundles	15
Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station	15
Verification of the direct transport code SHARK with the JRR-3M macro benchmark	15
Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks	15
Simulation on the fragmentation characteristics of molten core materials in SFRs using modified MPS method	15
Development of a flow sweeping mixing model for helical fuel rod bundles	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 the effect of non-uniform inflow on head characteristics of reactor coolant pumps	15
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer	15
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident	15
Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants	14
In-situ demonstration of engineered barrier system (In-DEBS) at KURT: Coupled thermal-hydro-mechanical behavior of buffer	14
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction	14
Influence of staggered guide vane on hydraulic performance of reactor coolant pump	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
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon	14
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR	14
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies	14
Development of a heat transfer model for the film boiling regime in a fouling layer	14
Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR	14
Performance evaluation of AMTEC/TEG coupling system for nuclear power space stations in space exploration	14
Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions	14

Highly scalable meshless multigrid solver for 3D thermal-hydraulic analysis of nuclear reactors	14
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction	14
Neutronic performance optimization of reconfigured TRIGA cores	14
Monte Carlo simulations of the water draining experimentof Giacint critical assembly	14
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL	14
Long-term reactivity control of accident tolerant fuel loaded marine small modular reactor using particle-type burnable poisons	14
On the use of average power in predicting radioisotope productions	14
Fuel cycle considerations for uranium, plutonium and minor actinide partitioning and transmutation	14
Resolved resonance region evaluations of n+ 206,207,208Pb for fast spectrum applications	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
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review	14
Development of NPP decommissioning cost estimation algorithm based on the CANDU structure	13
Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR	13
Study on influence of pad surface defects on lubrication characteristics of thrust bearing	13
Development of a cyberattack response planning method for nuclear power plants by using the Markov decision process model	13
ALFRED reactor and hybrid systems: A test case	13
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration	13
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors	13
Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation	13
Demand characteristics of component parts of Korean nuclear power plants depending on reactor type at the operation stage	13
A new equation for Bondarenko self-shielded cross section sensitivities to nuclide densities	13
Comparison analysis of density wave oscillation type two-phase flow instability of superheated and saturated boiling tubes	13
Stress analysis of shrink fitting process of ultra-thin reactor coolant pump rotor-can	13
Theoretical calculation of n+235U reaction	13
Risk analysis virtual ENvironment for dynamic event tree-based analyses	13
Investigation of small break LOCA with failure of the emergency core cooling system accident management in VVER-1000 reactor type	13
Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly	13
Layered target design method for global spectrum optimization of radioisotope production	13
Identification of the appropriate architecture of multilayer feed-forward neural network for estimation of NPPs parameters using the GA in combination with the LM and the BR learning algorithms	13
Conceptual design of the double tube burnable poison for the next generation small modular reactor	13
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast	13
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method	13
Evaluation of reflector design of ALLEGRO refractory core	13
Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions	13
Machine-learned force fields for thermal neutron scattering law evaluations	13
PCM-based uncertainty reduction in support of model validation for depletion calculations	13
Dynamic simulation of core power control for SPWR based on dynamic model bank	13
Research on condensation characteristics of supercritical carbon dioxide in Laval nozzle considering working condition of power cycles	12
Contribution to the verification of the MORET 5 code using the CROCUS reactor physics benchmark	12
Automatic prediction modeling for Time-Series degradation data via Genetic algorithm with applications in nuclear energy	12
Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding	12
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor	12
Investigation of single pressure point off-line correction in matrix-solved steam pipe network model for digital twins application	12
Transfer function modeling and simulation of HPR1000	12
Experimental study on flow-induced vibration of single rod in axial flow	12
Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core	12
Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis	12
Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube	12
Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)	12
Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field	12
Preliminary exploration of liquid metals turbulent heat flux model based on OpenFOAM solver: Second-order differential heat flux model	12
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques	12
Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM	12
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility	12
Simulation and experimental verification for Rh-SPND burnup effect	12
Editorial Board	12
A novel adaptive data condensation algorithm for preparing the input of a fuel rod performance code	12
Comparative study of meta-heuristic algorithms for reactor fuel reloading optimization based on the developed BP-ANN calculation method	12
Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method	12
Analysis of swarm flow and bubble residence time under pool scrubbing conditions	12
Simulation of an unprotected transient of the ALLEGRO reactor using the coupled neutronics/thermal-hydraulics system code KIKO3DMG/ATHLET3.0	12
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)	12
Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor	12
Scaling analysis for single-phase natural circulation under dynamic motion and its verification using MARS-KS code	11
Investigation of fission products distribution effected by spray system in PWR containment during severe accidents	11
Design of open-tank-in-pool-type educational critical assemblies using UO2 and U-7Mo fuels	11
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair	11
Rapid neutronic and thermal hydraulic analysis of LEU space reactor core	11
Development of transport solver based on Hybrid Finite Element Method in Griffin	11
Numerical investigation on effects of fuel rod with the position of bow deformation on the flow and heat transfer of PWR	11
Research and application of the neutronics and thermal–hydraulic coupling based on the MORE framework	11
Large-scale production by centrifugation of isotopically modified molybdenum for nuclear reactors and its cost evaluation	11
Damage performance analysis of prestressed concrete containments following a loss of coolant accident considering different external temperatures	11
Remote dismantling system using a digital manufacturing system and workpiece localization for nuclear facility decommissioning	11
Radiation damage analysis of the first generation VVER spent nuclear fuel casks	11
Nitrogen containing reductants for the corrosion control of alloys relevant to nuclear reactors	11
In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment	11
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au	11
Thermo-hydrodynamics of multiple drops impinging simultaneously on the grooved tubular surface and smooth cylindrical surface with different wettabilities	11
Optimal rule based fuzzy-PI controller for core power control of nuclear reactor	11
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification	11
Monte Carlo coupled Multi-Physics with spatially continuous material properties	11
Method of characteristics with a new Macro-track transport acceleration for complex general geometry	11
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions	11
Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element	11
Monte Carlo analysis of BWR geometries using a cycle check-up methodology	11
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor	11
Hybrid Data Assimilation methods, Part II: Application to the DYNASTY experimental facility	11
A finite element approach for nonlinear, transient heat conduction problems with convection, radiation or contact boundary conditions	11
Measurement of the neutron and gamma spectra at the training and research reactor AKR-2	11
Intelligent diagnosis of front-end redundancy for a control system based on physical correlation process	11
Experimental and numerical study on the transient heat transfer process for fluoride salt-to-air cooler	11
Primary coolant activity of 54Mn, 59Fe, 58Co, 60Co, and 51Cr in system integrated small and modular reactor	11
A three-dimensional PWR LBLOCA simulation using the CUPID code	11
Feasibility of Low-Enriched Uranium Fueled Nuclear Thermal Propulsion in the Low-Thrust Region Below 16klbf	11