Annals of Nuclear Energy

Article	Citations
An innovative method for building the model of oxidation resistance of Cr coatings	106
Experimental study on the influence of inclination on operating characteristics of secondary side passive residual heat removal system	99
Multi-generation point kinetics for subcritical systems	49
Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation	48
An application of sensitivity and representativity approach for the design of a 100%MOX BWR experimental program in ZPR	44
Source extrapolation scheme for Monte Carlo fission source convergence based on RMC code	42
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	42
Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method	41
VVER-1000/V446 spent fuel pool risk assessment and support through portable mitigating equipment	38
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	37
Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code	36
The gamma deposition matrix method for gamma heating calculations for LWRs	35
Experimental study on combustion characteristics of mixed sodium fire in a well-ventilated environment compared with confined space	34
Modeling elaborate dead time in reactor monitoring using SDE’s	32
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	32
Development and verification of Geant4-based parallel computing Monte Carlo simulations for nuclear logging applications	32
An experimental study related to axial constraint of fuel rod under LOCA conditions	30
Seismic experiments on short coaxial multi-layered cylindrical shells with fluid–structure interaction in fast reactors	30
Experimental modeling of slip velocity in an L-shape pulsed packed extraction column using response surface methodology	30
Editorial Board	29
Analysis of heat transfer and solidification within CANDU corium	29
CFD analysis of curvature and inclination effect on steam condensation in the presence of air	29
Calculate of an additional resistance with reverse flow in steam generator under steady-state conditions	29
Numerical simulation analysis of debris filtration in the bottom nozzle	28
Numerical simulation of safety injection and natural circulation in two containers by smoothed particle hydrodynamics on the effects of filling levels and thermal diffusivities	28

A new strategy for validating transient neutronic solver using the measurement data during the dynamic rod worth measurement process	28
Safety analysis of pressurized water reactors with annular fuel during different transients	28
Mapping radioactive environments by use of sparse Gaussian processes regression	27
Application of hybrid renewable energy for supplying the emergency power supply system in case of station blackout in nuclear power plant	27
Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor	26
Research on non-uniform control rod system of PWR	26
Researches on thermal hydraulics and fuel performance of ATFs during extreme steam generator tube failure without ECCS and DHRS in NuScale	26
Assessment of strategy robustness under disruption of objective in dynamic fuel cycle studies	26
A molten salt test loop for component and instrumentation testing	26
Neutronics and fuel cycle modeling of a thorium-fueled two-fluid molten salt iso-breeder reactor	25
Accelerated Monte Carlo perturbation calculation by surface recovery	25
Qualification activities of the spliced joint for CFETR	25
Application of the MOCABA algorithm and the FSTC tool for source term predictions during severe accident scenarios	25
Editorial Board	24
Assessment of different internal flow blockage scenarios for LFR fuel assemblies with different configurations	24
Editorial Board	24
Experimental study on fire resistance of electrical penetration assembly (EPA) under extreme circumstances	24
Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP	23
Problems on neutron production data of Be-9 in TENDL-2017 and -2019 deuteron sub-libraries	23
Path integral radiative transfer via polyline representation allowing GPU implementation	23
Experimental investigation on sodium leak behaviour through a pinhole	23
Dynamic modeling and characteristic analysis of the double-reactor and quadruple-turbine nuclear power system based on steam main-pipeline distribution characteristics	22
Mitigation of long-term station blackout accident of advanced boiling water reactors	22
Void effect research on MOX-fueled lead-cooled fast reactor	22
Editorial Board	22
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	21
Research of dynamic rod worth measurement technique based on the pin-by-pin response function	21
Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis	21
Extension of droplet/aerosol heat transfer model coupling Lagrangian approach in containment atmosphere under severe accident	21
Influence of nitrogen impurities on the characteristics of helium discharge at high pressure	21
Time dependent full-core multiphysics analysis of nuclear thermal propulsion reactors	20
Editorial Board	20
Probabilistic safety margin characterization of an integrated small modular reactor using MFM and adaptive polynomial chaos	20
Feasibility of innovative design concepts of Burnable poison pins for 24-month cycle PWR	20
Development of radiation characteristics analysis code system for geological disposal and application to vitrified waste disposal with various LWR burnup conditions	19
Editorial Board	19
The station blackout accident in a dual-cooled annular fuel of a VVER-1000 reactor with application of portable pumps for mitigating the accident	19
Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor	19
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	19
Uncertainty quantification and target accuracy assessment of nuclear data to effective neutron multiplication factor of heat pipe cooled reactor	19
A perturbation-based acceleration for Monte Carlo – Thermal Hydraulics Picard iterations. Part I: Theory and application to extruded BWR unit-cell.	19
Fission product depletion chain simplification method based on quantitative contribution function	19
A set of transient correlations for fast and unprotected loss of flow accident in VVER-1000 reactor using single-heated channel approach and Gene Expression Programming	19
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems	18
Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite	18
A continuous learning monitoring strategy for multi-condition of nuclear power plant	18
3DGShield: A new 3D gamma ray shielding code for arbitrary source and shield geometry based on point kernel technique	18
Editorial Board	18
On the simulation of neutron noise using a discrete ordinates method	18
Reduction of the source term of an assumed criticality accident in a fuel fabrication facility with solution system	18

The numerical analysis of the impact of CASTOR-1500 cask model simplifications on temperature distribution in the cask	18
Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident	17
Editorial Board	17
Numerical simulation on transient thermal and hydraulic characteristics in sodium pool of CEFR under OPT-SLOOP and OPT-RHROSL conditions	17
Flow distribution in the air cooler of HTGR passive cavity cooling system	17
Design of reactor physics experiments in support of chloride-fueled Molten Salt Reactor research & development	17
Development of a partitioned coupling method based on multi-scale data exchanges between porous and CFD solvers for a nuclear core	17
Clearance of building of a former uranium concentrates plant	17
Resilience assessment for nuclear power plants using Petri nets	17
Neutron spectrum measurements inside a self-shielded cyclotron during 18F production using a single-cylindrical neutron spectrometer with gold and indium activation foils	16
Optimised structured state feedback controller for zone power and bulk power control of PHWRs	16
A scaling method based on the density variation for natural circulation in lead cooled fast reactors	16
Monte Carlo based absolute efficiency calibration of power reactor spent fuel NDA measurements	16
Investigation on radioisotopes evolution in the fuel of Lead-Bismuth eutectic (LBE) cooled SPARK-NC core	16
Analysis of the influence of bottom flow holes in control rod guide tubes on flow field and control rod displacement	16
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	16
Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor (SD-TMSR)	16
A novel method for rapid calculation of moderated neutron spectrum and its application in deep penetration	16
Development of active and passive reactivity control systems for a fast spectrum small modular reactor	16
Insights into calculating Reference Discontinuity Factors with Serpent Monte Carlo code	16
Development of a friction factor correlation for a foam flow in a horizontal circular pipe	16
Research on global neighbor list method in Monte Carlo code RMC	16
Towards a Monte Carlo simulation of a pebble bed type high temperature gas cooled reactor using Geant4	16
Deep heterogeneous joint architecture: A temporal frequency surrogate model for fuel performance codes	16
Fault diagnosis and degree evaluation of steam generator heat transfer tube rupture based on hybrid method	16
Radioactive study of oxidation-corrosion materials activated by neutron in lead-bismuth eutectic reactors	16
General solution of Bateman equations using Cauchy products and the Theory of Divided Differences	15
Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark	15
Simulation of in-core neutron monitoring with U-235 micro fission chamber for CiADS-like LFR	15
Study on the thermo-hydraulic behaviors within a CiADS 61-pin wire-wrapped fuel assembly under porous blockage conditions based on LBEblockageFoam	15
Power distribution bias from equilibrium xenon effects when insufficient neutron histories per cycle are used in Monte Carlo simulation of CANDU6	15
Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations	15
Development of mechanistic model for CHF based on boiling crisis process	15
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	15
A nodal method based on CMFD for pin-by-pin SP3 calculation	15
A study on the optimization through the evaluation of radiation exposure by scenarios during steam generator dismantling	15
Pool scrubbing in unit 1 of fukushima daiichi	15
Pulse operation mode of inertial electrostatic plasma confinement devices	15
Experimental study on the influence of initial state parameters on the start-up and heat transfer characteristics of separated heat pipe system	15
Addendum to [Giaccardi et al., 2024]: On the definition of the escape rate coefficient	14
Frictional pressure drop correlation of steam-water two-phase flow in helically coiled tubes	14
Polynomial interpolation cross-section parameterization method with the RMC Monte Carlo code	14
Dynamic mode decomposition for subcriticality measurement using measured data at single location	14
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	14
Research on sensor fault tolerance technology in nuclear power plant control system	14
Assessment of wall models for coarse-mesh RANS simulations	14
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	14
THAI experiments on iodine behavior in a room chain representing flow conditions in large containments	14
Modelling of the expansion phase of Sodium fast reactor severe accident	14
Stability analysis of a parallel channel-loop system with single-phase natural circulation under asymmetric conditions	14
Editorial Board	14
Guide vane angle and reactor coolant pump performance during idling	14
Investigation on swelling characteristics of GMZ bentonite with different initial water contents	14
CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change model	14
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	14
Moderation device design for detecting hidden highly enriched uranium based on D-T neutron generator	14
Analysis for the use of thorium based fuel in LWRs	14
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	14
Influence of PCHE size and types on thermodynamic and economic performance of supercritical carbon dioxide Brayton cycle for small modular reactors and its optimization	14
Mitigating the numerical xenon instability in deterministic reactor burnup calculations	14
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	14
Comparative study of flow and heat transfer characteristics of HCF rod bundles in rectangular and triangular arrangement	13
Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD	13
Numerical solution of a comprehensive form of convection–diffusion equation for binary isotopes in the gas centrifuge	13
Model based security verification of Cyber-Physical System based on Petrinet: A case study of Nuclear power plant	13
Effect of impact velocity on time-dependent force and droplet pressure in high-speed liquid droplet impingement	13
New computational technique based on Bernstein polynomials and higher order finite difference schemes for temporal and spatial reactor calculations	13
Development of a WENO-type numerical solver for two-phase two-fluid six-equation model	13
Robust fuzzy gain scheduling power control of a generation IV nuclear reactor	13
Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test	13
Thermal-hydraulic study in a wire-wrapped 19-rod bundle based on an isotropic four-equation model	13
Predicting and optimizing the thermal-hydraulic, natural circulation, and neutronics parameters in the NuScale nuclear reactor using nanofluid as a coolant via machine learning methods through GA, PSO	13
Steady and transient solutions of neutron diffusion equations via computational methods based on Hartley series and higher order finite difference schemes	13
Evaluation of filtered containment venting system (FCVS) effects on severe accident of a WWER1000 plant	13
Modelling of fission products release in VERDON-1 experiment with cGEMS: Coupling of severe accident code MELCOR with GEMS thermodynamic modelling package	13
Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation	13
An efficient numerical method for fractional neutron diffusion equation in the presence of different types of reactivities	13
Radiation survey for Taiwan research reactor vessel	12
Utilization of random forest classifier and artificial neural network for predicting the acceptance of reopening decommissioned nuclear power plant	12
Feasibility assessment of heat pipe space reactor passive start-up without external neutron source	12

Analysis of a PSB-VVER small break LOCA experiment with APROS and TRACE system codes	12
Experimental study on leakage of high-energy fluids through narrow elliptical slits	12
Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method	12
Numerical simulation of involute-plate research reactor flow behavior using RANS, LES and DNS	12
LSTM-GCN based multidimensional parameter relationship analysis and prediction framework for system level experimental bench	12
Development of the thermal hydraulic analysis code, TASS/SMR-S, under multi-dimensional motion for a reactor under inclination and rolling conditions	12
A model fine-tuning approach for robust anomaly detection and isolation in multi-sensor system of nuclear power plants	12
Integral experiments in the VENUS-F reactor	12
Research on reliability assessment approach of marine passive safety system based on improved Kriging model and SORM	12
Development of a solidification blockage discriminant model in filling pipelines	12
Evaluation of ATFs in core degradation of a PWR in unmitigated SBLOCA	12
Variable universe fuzzy control of once-through steam generator feedwater	12
Extension of SCALE/Sampler’s sensitivity analysis	12
Impact of the TRISO fuel homogenisation approximation in the MHTGR	12
A PWR core power control using optimized PID controller with SQP based on control rod positioning and variable coolant flow rate	12
Study on neutron spectrum unfolding method of organic scintillation measurement based on iterative regularization	12
Experiments on axial-flow-induced vibration of a free-clamped/clamped-free rod for light-water nuclear reactor applications	12
Impact of radioactive emissions from the Laguna Verde nuclear power plant using CALPUFF	12
Investigation of molten fuel coolant interaction with simulated corium in sodium	12
Online learning based neural network adaptive controller for efficient power tracking of PWR type reactor with unknown internal dynamics	12
Photon and thermal neutron shielding behaviors of aluminum calcium fluoroborate glass modified with barium oxide: FLUKA Monte Carlo, XCOM and experimental investigations	12
Evaluation of the fitting-based reactivity-equivalent physical transformation method for double heterogeneity phenomena of plate-type fuel in pressurized water reactors	12
An approach to the experimental validation of the fission multiplying blanket of hybrid fusion fission systems	12
Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient	12
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems	12
Iodine source term assessment as result of iodine spiking and mass transfer phenomena during a SGTR transient using MELCOR 2.2 and CATHARE 2 codes	11
Accuracy and efficient solution of helical coiled once-through steam generator model using JFNK method	11
Operator actions evaluation for MSGTR accident mitigation	11
Numerical simulation of the early startup period of heat pipe cooled reactor system from the room temperature state	11
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	11
Nuclear data sensitivity and uncertainty analysis using a set of benchmarks containing	11
Study on flow and heat transfer characteristics of supercritical CO2 inside horizontal tube under ocean rolling condition	11
Study of the stability of iodine oxides (IxOy) aerosols in severe accident conditions	11
Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients	11
Numerical analysis of turbulent mixed convection heat transfer of molten salt in an inclined cooling tube	11
BEAVRS pin-by-pin calculations with Ants-SUBCHANFLOW-SuperFINIX code system	11
A review of uncertainties in the assessment of the radiological impact of liquid releases to the Ignalina NPP cooling pond lake Drūkšiai	11
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	11
Study on adaptive heat transfer performance of high temperature heat pipe	11
Development of angle-dependent linear source approximation for three-dimensional method of characteristics transport analysis method in STREAM	11
Natural convection compound heat transfer enhancement by discrete rings and the chimney effect in a vertical cylinder	11
The neutron number probability distribution in coupled lumped assemblies	11
Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON	11
On Simplified Spherical Harmonics (SPN) and Generalized SPN (GSPN) formulations	11
Dynamic modeling and intelligent hybrid control of pressurized water reactor NPP power transient operation	11
Development of a fast thermal-hydraulic model to simulate heat and fluid flow in MNSR	11
Neutronic analysis of silicon carbide Cladding-ATF fuel combinations in small modular reactors	11
Implementation of chrome oxidation model into best-estimate system code for accident tolerant fuel	11
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	11
Seismic fragility analysis of nuclear containment structure under chloride-induced reinforcing steel corrosion conditions	11
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	11
Numerical study on heat transfer characteristics of LBE cross flow tube bundle under rolling conditions	11
Development of nuclear fuel assembly 3D reduced model and modal analysis	11
Classification of group structures for a multigroup collision probability model using machine learning	11
Neighbor-informed burnup correction for gadolinia depletion in pin-homogenized core calculation	11
CMT and PBL study in the high-pressure phase on the advance core-cooling mechanism experiment with RELAP 5	11
Comparison of BANDI-60 core designs using Pyrex burnable absorber and annular fuel embedding gadolinia wire	11
Influence of helix angle on flow and heat transfer characteristics of lead–bismuth flow in helical-coiled tube bundles	11
Behaviors of type-I instabilities in natural circulation with a heating channel under ocean conditions	11
Validation of the fast reactor plant dynamics analysis code Super-COPD using FFTF loss of flow without scram test #13	11
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	11
Research on optimization of key thermal parameters of the secondary loop of PWR based on improved BP neural network	11
Theoretical study on the Passively Decay Heat Removal System and the primary loop flow rate of NuScale SMR	10
Experimental study on gas mixing and transport induced by external cooling on large-scale facility	10
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration	10
Development and verification of multigroup advanced semi analytic nodal method solver for HTGR analysis with MHTGR-350	10
Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic	10
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: Methodology demonstration	10
Comparing the time-eigenvalues of the natural mode equation by weight balancing and α-k methods	10
Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid	10
Experimental study on the plate-type fuel melting behavior based on alternative materials	10
Research of VDT scheme for porous media thermal-hydraulics analysis of plate-type fuel assembly	10
Large-break LOCA analysis of CSR1000	10
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	10
Modal and structural analysis on a main feed water regulating valve under different loading conditions	10
The combination method of functional failure and device fault for passive safety system in nuclear power plant	10
Improved subgroup method coupled with particle swarm optimization algorithm for intra-pellet non-uniform temperature distribution problem	10
Dynamic analysis of dry storage canister and the spent fuels inside under vertical drop in HTR-PM	10
Malfunction diagnosis based on residence time distribution of radiotracer signals in industrial processes using machine learning techniques	10
Machine learning application to single channel design of molten salt reactor	10
Online inventory modeling of a CANDU-6 reactor for nuclear forensic applications	10
Study on heat transfer characteristics of liquid droplet radiator: With VS without inter-droplets coupling	10
Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review	10
Investigation of Anderson acceleration in neutronics-thermal hydraulics coupled direct whole core calculation	10
Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition	10
Experimental and theoretical study on fluidelastic instability of tube bundles subjected to cross-flow in the parallel direction	10
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR	10
Research on the clearance flow between stator and rotor cans in canned motor RCP	10
The Transient Multi-Level method for Monte Carlo reactor statics calculations	10
Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731	10
Steady-state analysis of Xi’an Pulse Reactor based on the multi-physics coupling method	10
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction	10
Study on flow regime prediction model for water-cooled reactor core based on machine learning algorithms	10
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system	9
Sensitivity study of thermal-hydraulic nodalization for MELCOR simulations of severe accidents in a pressurized water reactor	9