Annals of Nuclear Energy

Article	Citations
Experimental study on the influence of inclination on operating characteristics of secondary side passive residual heat removal system	147
Multi-generation point kinetics for subcritical systems	113
Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation	61
An application of sensitivity and representativity approach for the design of a 100%MOX BWR experimental program in ZPR	52
Study on neutron shielding performance of hot cell shielding door for nuclear power plant	50
Source extrapolation scheme for Monte Carlo fission source convergence based on RMC code	48
Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method	45
VVER-1000/V446 spent fuel pool risk assessment and support through portable mitigating equipment	43
Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR	42
The gamma deposition matrix method for gamma heating calculations for LWRs	40
Evaluation of power distribution calculation of the very high temperature reactor critical assembly (VHTRC) with Monte Carlo MVP3 code	40
Experimental study on combustion characteristics of mixed sodium fire in a well-ventilated environment compared with confined space	40
Development and verification of Geant4-based parallel computing Monte Carlo simulations for nuclear logging applications	37
Experimental analysis of boron dilution transient flow mixing characteristics based on planar laser induced fluorescence measurement	34
An experimental study related to axial constraint of fuel rod under LOCA conditions	33
Seismic experiments on short coaxial multi-layered cylindrical shells with fluid–structure interaction in fast reactors	33
Modeling elaborate dead time in reactor monitoring using SDE’s	33
CFD analysis of curvature and inclination effect on steam condensation in the presence of air	32
Editorial Board	31
Calculate of an additional resistance with reverse flow in steam generator under steady-state conditions	30
Numerical simulation analysis of debris filtration in the bottom nozzle	30
A new strategy for validating transient neutronic solver using the measurement data during the dynamic rod worth measurement process	30
Safety analysis of pressurized water reactors with annular fuel during different transients	29
Assessment of strategy robustness under disruption of objective in dynamic fuel cycle studies	29
A molten salt test loop for component and instrumentation testing	29

Mapping radioactive environments by use of sparse Gaussian processes regression	29
Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor	29
Application of hybrid renewable energy for supplying the emergency power supply system in case of station blackout in nuclear power plant	29
Research on non-uniform control rod system of PWR	29
Application of the MOCABA algorithm and the FSTC tool for source term predictions during severe accident scenarios	28
Editorial Board	28
Researches on thermal hydraulics and fuel performance of ATFs during extreme steam generator tube failure without ECCS and DHRS in NuScale	28
Accelerated Monte Carlo perturbation calculation by surface recovery	28
Experimental study on fire resistance of electrical penetration assembly (EPA) under extreme circumstances	27
Experimental investigation on sodium leak behaviour through a pinhole	26
Assessment of different internal flow blockage scenarios for LFR fuel assemblies with different configurations	26
Editorial Board	26
Problems on neutron production data of Be-9 in TENDL-2017 and -2019 deuteron sub-libraries	26
Void effect research on MOX-fueled lead-cooled fast reactor	25
Path integral radiative transfer via polyline representation allowing GPU implementation	25
Mitigation of long-term station blackout accident of advanced boiling water reactors	24
Extension of droplet/aerosol heat transfer model coupling Lagrangian approach in containment atmosphere under severe accident	24
Editorial Board	24
Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis	24
Dynamic modeling and characteristic analysis of the double-reactor and quadruple-turbine nuclear power system based on steam main-pipeline distribution characteristics	24
Time dependent full-core multiphysics analysis of nuclear thermal propulsion reactors	23
Research of dynamic rod worth measurement technique based on the pin-by-pin response function	23
Fission product depletion chain simplification method based on quantitative contribution function	23
Probabilistic safety margin characterization of an integrated small modular reactor using MFM and adaptive polynomial chaos	23
Editorial Board	23
Influence of nitrogen impurities on the characteristics of helium discharge at high pressure	23
Development of radiation characteristics analysis code system for geological disposal and application to vitrified waste disposal with various LWR burnup conditions	22
Research and validation on the numerical algorithm of mechanical module in a transient fuel rod performance code for fast reactor	22
A perturbation-based acceleration for Monte Carlo – Thermal Hydraulics Picard iterations. Part I: Theory and application to extruded BWR unit-cell.	22
Editorial Board	21
Editorial Board	21
On the simulation of neutron noise using a discrete ordinates method	21
Uncertainty quantification and target accuracy assessment of nuclear data to effective neutron multiplication factor of heat pipe cooled reactor	21
A continuous learning monitoring strategy for multi-condition of nuclear power plant	21
Technical Note: Development of a generalized source model for flux estimation in nuclear reactors	21
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems	21
The numerical analysis of the impact of CASTOR-1500 cask model simplifications on temperature distribution in the cask	21
Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident	20
Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite	20
Flow distribution in the air cooler of HTGR passive cavity cooling system	20
Development of a partitioned coupling method based on multi-scale data exchanges between porous and CFD solvers for a nuclear core	20
Reduction of the source term of an assumed criticality accident in a fuel fabrication facility with solution system	20
Clearance of building of a former uranium concentrates plant	19
Optimised structured state feedback controller for zone power and bulk power control of PHWRs	19
Machine learning approach for predicting nuclide composition in nuclear fuel: Bypassing traditional depletion and transport calculations	19
Numerical simulation on transient thermal and hydraulic characteristics in sodium pool of CEFR under OPT-SLOOP and OPT-RHROSL conditions	19
Research on global neighbor list method in Monte Carlo code RMC	19
Towards a Monte Carlo simulation of a pebble bed type high temperature gas cooled reactor using Geant4	19
Editorial Board	19
A scaling method based on the density variation for natural circulation in lead cooled fast reactors	19

A model fine-tuning approach for robust anomaly detection and isolation in multi-sensor system of nuclear power plants	18
Research on least-square solver for physics-informed neural network in thermal-hydraulic analysis of nuclear reactors	18
The two point Feynman-α theory: Theory and practice of Ex-Core reac	18
Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731	18
Development of a two-phase flow solver with drift-flux model based on OpenFOAM: Validation against single/two-phase and boiling flow	18
Neutron transmission measurements for silica glass at the KURNS-LINAC	18
Thermal safety analysis of thermionic space nuclear reactor startup on orbit	18
Temperature flattening and thermoelectric conversion modeling of TOPAZ-II thermionic reactor	18
Semi-automatic image annotation using 3D LiDAR projections and depth camera data	18
Capability for processing photonuclear data in nuclear data processing code NECP-Atlas	18
Experimental study on the plate-type fuel melting behavior based on alternative materials	18
Development of mechanistic model for CHF based on boiling crisis process	18
Turbulent random loads on wire wrapped fuel rod bundle: theory, simulations and formulas	18
Editorial Board	18
Homogeneity and isotropy restoration (HIRE)-Theoretic multigroup neutron transport equations and Two-Level p-CMFD acceleration scheme	18
Radiation survey for Taiwan research reactor vessel	18
Generation of high-resolution thermal scattering laws for solid moderators using fast Fourier transforms	18
Fault diagnosis and degree evaluation of steam generator heat transfer tube rupture based on hybrid method	18
Multi-objective reinforcement learning-based approach for pressurized water reactor optimization	18
Insights into calculating Reference Discontinuity Factors with Serpent Monte Carlo code	17
Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid	17
Development and verification of an efficient collision algorithm for seismic analysis of fast reactor core assemblies	17
A study on the optimization through the evaluation of radiation exposure by scenarios during steam generator dismantling	17
Monte Carlo based absolute efficiency calibration of power reactor spent fuel NDA measurements	17
Development of a friction factor correlation for a foam flow in a horizontal circular pipe	17
Steady-state thermal–hydraulic analysis of an NTP reactor core based on the porous medium approach	17
Power distribution bias from equilibrium xenon effects when insufficient neutron histories per cycle are used in Monte Carlo simulation of CANDU6	17
Development of active and passive reactivity control systems for a fast spectrum small modular reactor	17
Investigation on radioisotopes evolution in the fuel of Lead-Bismuth eutectic (LBE) cooled SPARK-NC core	17
Evaluating uncertainties: Heat transfer parameter effects on stratified melt pool simulation	17
Radioactive study of oxidation-corrosion materials activated by neutron in lead-bismuth eutectic reactors	16
Deep heterogeneous joint architecture: A temporal frequency surrogate model for fuel performance codes	16
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors	16
Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON	16
Analysis of the influence of bottom flow holes in control rod guide tubes on flow field and control rod displacement	16
Research on core thermal hydraulic parameters prediction based on the improved GAN method and combined ANN model	16
Performance of potentiometric oxygen sensors with LSM composite electrode in saturated oxygen liquid LBE	16
Research on fuzzy weighted gain scheduling water level control system of U-tube steam generator	16
Malfunction diagnosis based on residence time distribution of radiotracer signals in industrial processes using machine learning techniques	16
Neutron spectrum measurements inside a self-shielded cyclotron during 18F production using a single-cylindrical neutron spectrometer with gold and indium activation foils	16
Numerical assessment for entry condition of severe accident management guidelines in a Swedish nuclear power plant	16
Steady-state analysis of Xi’an Pulse Reactor based on the multi-physics coupling method	16
Pool scrubbing in unit 1 of fukushima daiichi	15
Pulse operation mode of inertial electrostatic plasma confinement devices	15
Study on the thermo-hydraulic behaviors within a CiADS 61-pin wire-wrapped fuel assembly under porous blockage conditions based on LBEblockageFoam	15
Dynamic mode decomposition for subcriticality measurement using measured data at single location	15
Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark	15
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator	15
Stability analysis of a parallel channel-loop system with single-phase natural circulation under asymmetric conditions	15
Analysis for the use of thorium based fuel in LWRs	15
Robust fuzzy gain scheduling power control of a generation IV nuclear reactor	15
A nodal method based on CMFD for pin-by-pin SP3 calculation	15
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants	15
Modelling of the expansion phase of Sodium fast reactor severe accident	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
Moderation device design for detecting hidden highly enriched uranium based on D-T neutron generator	14
Editorial Board	14
CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change model	14
Design of reactor physics experiments in support of chloride-fueled Molten Salt Reactor research & development	14
Steady and transient solutions of neutron diffusion equations via computational methods based on Hartley series and higher order finite difference schemes	14
Development of a WENO-type numerical solver for two-phase two-fluid six-equation model	14
Low intensity radiation image restoration method based on Bayesian maximum posterior framework	14
Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS	14
Polynomial interpolation cross-section parameterization method with the RMC Monte Carlo code	14
Spatially-variant isotope production burnup modeling in a CANDU-6 reactor for nuclear treaty monitoring	14
Efficient adsorption and in situ solidification of cesium from aqueous solution using mesoporous MnO2@SBA-15	14
Effect of impact velocity on time-dependent force and droplet pressure in high-speed liquid droplet impingement	14
New computational technique based on Bernstein polynomials and higher order finite difference schemes for temporal and spatial reactor calculations	14
Mitigating the numerical xenon instability in deterministic reactor burnup calculations	14
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes	14
THAI experiments on iodine behavior in a room chain representing flow conditions in large containments	14
Assessment of wall models for coarse-mesh RANS simulations	14
Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations	14
Intergranular fracture induced by helium bubbles segregation in NiFe single-phase concentrated solid solution alloys	14
Neutronics/thermal-hydraulics/fuel-performance coupling for light water reactors and its application to accident tolerant fuel	14
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	14
Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients	13
Feasibility assessment of heat pipe space reactor passive start-up without external neutron source	13

Integral experiments in the VENUS-F reactor	13
An improved zigzag-type printed circuit heat exchanger for supercritical CO2 Brayton cycles	13
Numerical solution of a comprehensive form of convection–diffusion equation for binary isotopes in the gas centrifuge	13
Neutronic analysis of silicon carbide Cladding-ATF fuel combinations in small modular reactors	13
An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad	13
Nuclear data sensitivity and uncertainty analysis using a set of benchmarks containing	13
Model based security verification of Cyber-Physical System based on Petrinet: A case study of Nuclear power plant	13
Experiments on axial-flow-induced vibration of a free-clamped/clamped-free rod for light-water nuclear reactor applications	13
Influence of helix angle on flow and heat transfer characteristics of lead–bismuth flow in helical-coiled tube bundles	13
A state-of-the-art review on performance measurement petri net models for safety critical systems of NPP	13
Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test	13
Extension of SCALE/Sampler’s sensitivity analysis	13
Comparison of BANDI-60 core designs using Pyrex burnable absorber and annular fuel embedding gadolinia wire	13
Study of the stability of iodine oxides (IxOy) aerosols in severe accident conditions	13
Online learning based neural network adaptive controller for efficient power tracking of PWR type reactor with unknown internal dynamics	13
Study on neutron spectrum unfolding method of organic scintillation measurement based on iterative regularization	13
Study on flow and heat transfer characteristics of supercritical CO2 inside horizontal tube under ocean rolling condition	13
Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation	13
Development of a fast thermal-hydraulic model to simulate heat and fluid flow in MNSR	13
On Simplified Spherical Harmonics (SPN) and Generalized SPN (GSPN) formulations	13
Modelling and simulations of reactor neutron noise induced by mechanical vibrations	12
Experimental study on treatment of simulated radioactive waste by thermal plasma: Temporal evaluation of stable Co and Cs	12
Groundwater path radiological impact assessment for the derivation of specific clearance levels for landfill disposed waste at Ignalina NPP	12
Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method	12
Development of a solidification blockage discriminant model in filling pipelines	12
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems	12
Analysis of a PSB-VVER small break LOCA experiment with APROS and TRACE system codes	12
Research for axial power distribution control of a space nuclear reactor based on nonlinear model	12
Thermal hydraulic analysis of a deformed SFR fuel assembly using CFD	12
Experimental investigation of pool boiling heat transfer and bubble dynamics for the downward facing heating	12
Underlying mathematical relations for efficient COMET response expansion coefficient and core calculations	12
Development and verification of the coupling code of discrete ordinates and Monte Carlo methods	12
A review of uncertainties in the assessment of the radiological impact of liquid releases to the Ignalina NPP cooling pond lake Drūkšiai	12
Demonstration of combined reduced order model and deep neural network for emulation of a time-dependent reactor transient	12
Research on reliability assessment approach of marine passive safety system based on improved Kriging model and SORM	12
An approach to the experimental validation of the fission multiplying blanket of hybrid fusion fission systems	12
Experimental investigation on pressure drop characteristics of two-phase flow in a rod bundle geometry under high pressure conditions	12
Comparing the time-eigenvalues of the natural mode equation by weight balancing and α-k methods	12
Impact of the extended computational domain at inlet and outlet on natural convection in a vertical rectangular channel	12
Subchannel analysis of critical heat flux in radially Non-uniform heated rod assembly at low flow rate	12
A review of the current nuclear data performance assessments in advanced nuclear reactor systems	12
Research on optimization of key thermal parameters of the secondary loop of PWR based on improved BP neural network	12
LSTM-GCN based multidimensional parameter relationship analysis and prediction framework for system level experimental bench	12
Investigation of molten fuel coolant interaction with simulated corium in sodium	12
Research on the clearance flow between stator and rotor cans in canned motor RCP	12
An improved analysis of the OECD/NRC PWR MOX/UO2 core transient benchmark with PARCS/Serpent	12
BEAVRS pin-by-pin calculations with Ants-SUBCHANFLOW-SuperFINIX code system	12
Development of the thermal hydraulic analysis code, TASS/SMR-S, under multi-dimensional motion for a reactor under inclination and rolling conditions	12
Model inadequacy in fuel performance code calibration: Derivative-based parameter uncertainty inflation	12
Microstructure and mechanical properties of the solidified melt obtained by the in-pile test	12
Estimation of weight window parameters based on recursive Monte Carlo approach for reactor shielding problems	11
Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F	11
A new sampling scheme combining maximum entropy and moment matching techniques for reactor physics uncertainty quantification	11
Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis	11
Implementation of chrome oxidation model into best-estimate system code for accident tolerant fuel	11
Calculation scheme for thermal neutron scattering cross-sections of hydrogenous molecules in liquid and solid phases by molecular dynamics	11
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system	11
Nuclear education programs with reactor laboratory experiments at zero-powered research reactor facilities in Japan	11
Mixed convective and radiative heat transfer of LiF-BeF2-ThF4-UF4 in a vertical circular tube	11
Gas-liquid flow regime identification via a non-intrusive optical sensor combined with polynomial regression and linear discriminant analysis	11
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors	11
Prediction of stress-fatigue life on the impeller of the reactor coolant pump based on fluid-thermal-structure interaction method	11
Hydrothermal-processed volcanic ash-based geopolymers for immobilization of sodium salt wastes containing Cs	11
Preliminary neutronics and thermal analysis of a heat pipe cooled traveling wave reactor	11
Impact of the resonance elastic scattering on reactor-core physics calculation results based on the deterministic method	11
Seismic fragility analysis of nuclear containment structure under chloride-induced reinforcing steel corrosion conditions	11
Review of research and capabilities of 500 kW research reactor at the Ohio State University	11
High-efficiency simulation of VENUS-3 neutron-shielding problem with an automatic and enhanced hybrid Monte-Carlo-Deterministic method	11
Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly	11
Numerical-analytical solutions of the fractional point kinetic model with Caputo derivatives	11
Assessing dependence in human reliability analysis using probabilistic linguistic term sets	11
Neighbor-informed burnup correction for gadolinia depletion in pin-homogenized core calculation	11
A calculation model for radionuclide dispersion in the ocean and its credibility evaluation	11
Effects of rolling motion on helical coil once-through steam generator thermal-hydraulic characteristics	11
Depletion chain simplification using pseudo-nuclides	11
Evaluation on 131I production based on molten salt reactor off-gas extraction	11
The influence of internal flow on fluidelastic instability of a flexible tube in tube bundles subjected to two-phase cross-flow	11
Development and verification of the hexagonal core simulation capability of the NECP-X code	11
Behaviors of type-I instabilities in natural circulation with a heating channel under ocean conditions	11
Generation method and verification of pebble type VHTR multigroup cross sections based on OpenMC	11
Evaluation of hydrogen generation from feeder pipes of CANDU reactor	11
An approach for performing resolved and unresolved resonance evaluation based on few or none experimental data available: Application to unstable and short-lived isotopes	11
One-dimensional transient analysis of the dual-fluid reactor system	11
Study on adaptive heat transfer performance of high temperature heat pipe	11
Fine Mesh Finite Difference acceleration method based on the Generalized Equivalence Theory for the 2-D MOC transport calculation	11
Impact of experimental effects on a resolved resonance evaluation for practical applications	11
A systematic approach in the development of generic biosphere conceptual models for groundwater release into the Korean biosphere system from a spent nuclear fuel deep geological repository	11
From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction	10
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory	10
Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition	10
Dynamic analysis of dry storage canister and the spent fuels inside under vertical drop in HTR-PM	10
Development and verification of multigroup advanced semi analytic nodal method solver for HTGR analysis with MHTGR-350	10
Study on heat transfer characteristics of liquid droplet radiator: With VS without inter-droplets coupling	10
Experimental and theoretical study on fluidelastic instability of tube bundles subjected to cross-flow in the parallel direction	10
The combination method of functional failure and device fault for passive safety system in nuclear power plant	10