Nuclear Engineering and Design

Article	Citations
Acoustic field study of ultrasonic transducers for nuclear pipelines using an improved Gaussian beam method	60
Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations	53
Experimental study of the transient boiling phenomenon on a vertically placed ribbon	42
Neutronic characteristics of the VVER-1000 fuel assembly with mechanical spectral shift regulation	40
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	39
Effective thermal conductivity prediction of dispersion nuclear fuel elements based on deep learning and property-oriented inverse design	38
An inversion model for burnup history of spent fuels in pebble bed HTGR based on optimization algorithm	38
Interaction characteristics of subcooled water jet with high-pressure upward into high-temperature oil in a confined space	38
Optimization of uranium and uranium-thorium fuel utilization in pebble bed for PeLUIt-10 reactor using PEBBED code	33
A comprehensive review of pulsed research reactors: Focus on Russian periodic fast reactors	32
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	31
Impact of including fuel performance as part of core reload optimization: Application to power uprates	30
Fabrication of surrogate oxide spent fuel with various cracking patterns and design of an axial gas transport apparatus	30
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	28
Editorial Board	28
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	27
Editorial Board	27
Conceptual design and analysis of a combined passive cooling system for both reactor and spent fuel of the pool-vessel reactor system	26
Modeling and simulation of the radiolytic deuterium and oxygen generation in heavy water reactors	26
Editorial Board	25
Analysis and evaluation of the irradiated dimensional and volume change behavior of nuclear graphites	24
Safety analysis and evaluation of transport and storage container for very Low-Level liquid radioactive waste	24
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation	24
Editorial Board	23
Steam flows in concrete cracks: Thermal behaviour	23

Time averaged tomographic measurements before and after dryout in a simplified BWR subchannel geometry	23
Nuclear reactor Thermal-Hydraulics Special and prospective topical areas	22
On the importance of consistency of multiple-level modeling of multiphase flow in reactor systems	22
A simple correlation to estimate agglomerated debris formation based on experiments of melt jet-breakup using a metallic melt	22
Development of the reactor core isolation cooling system model for the extended station black-out accident	22
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	22
Error in bubble velocity measurement using 4-sensor void probe due to interface deformation	21
Effects of inclined condition on LOCA for a small offshore reactor with OTSG	21
Editorial Board	21
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	21
Uncertainty and disturbance estimator based spatial power control of advanced heavy water reactor	20
An estimation method for near real-time accountancy of partitioned materials during chopper operations of used metallic nuclear fuel processing	20
Experimental study on condensation heat transfer characteristics in C-shaped tube under rolling conditions	20
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	19
Editorial Board	19
Editorial Board	19
Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code	19
Acceleration calibration method for the drop test of radioactive package based on the rebound of specimen	19
Core physical conceptual design of small reactor for unmanned underwater vehicle	18
Investigation of reactivity control strategies for a micro-transportable gas-cooled thermal reactor	18
Optimization of preparation process and study on the properties and microstructures of nuclear natural graphite powder for HTR pebble fuel elements	18
Experimental and theoretical study on formation of interfacial waves on liquid film of annular two-phase flow	18
Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds number	18
Autonomous search investigation for radioactive leaked source based on an updated infotaxis method during nuclear emergency rescue	18
Foreword	18
A standard capsule design for structural material testing in the Advanced Test Reactor	17
Design of an ultra-compact imaging chamber and radiation beamstop for a neutron radiography system employing particle transport	17
Numerical analysis of a small-scale novel vortex tower integrated with heat source for Nuclear Application	17
Modeling and comparative analysis of changeover of homogeneous and heterogeneous core of BN-1200 reactor to equilibrium mode	17
Experimental investigation on distribution of boric acid in a vertical 1 × 2 rod array channel	17
Mechanism and risk assessment of baffle-jetting-induced vibrations in fuel rods	17
Core design: Review & perspectives in Spain	16
Theoretical analysis about model simplifications and boundary conditions on two-phase flow instability of parallel heated tube systems	16
Power transient critical heat flux in a narrow rectangular channel under downward flow	16
Editorial Board	16
Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR	16
A newly proposed data assimilation framework to enhance predictions for reflood tests	16
Editorial Board	16
Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor	15
Comparison and optimization of heat transfer models in reactor channel under the rolling condition	15
Development process of FPGA based technology for control rod drive systems of experimental power reactor	15
Effects of fuel relocation on fuel performance and evaluation of safety margin to 10CFR50.46c ECCS acceptance criteria in APR1400 plant	15
Theoretical analysis of the flow stability of HTGR supercritical steam generators using dimensionless numbers	15
Status of benchmark exercises in the frame of the NUGENIA QUESA project	15
The progress on the 3D whole-core neutronics calculation of PANGU code	15
A comprehensive analysis of thermal–hydraulic signatures in neutron noise of WWER-type reactors	15
Influence of thermal effects on the cavitation of orifices in nuclear power plants	15
Editorial Board	15
Experimental study on flow rate distortion of natural circulation reduced-height scaling	14
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	14

Analysis of a test facility for transients in a supercritical water-cooled reactor using dynamic system scaling methodology	14
Near regional geology of Pantai Gosong NPP Site, West Kalimantan, Indonesia: Capable fault and geotechnical hazards assessment	14
Uncertainty quantification (UQ) for CFD simulation of OECD-NEA cold leg mixing benchmark	14
SOURCE a computer code for fission-product partitioning and release from fuel	14
A proposed refueling scheme for the modular pebble bed reactor	14
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres	14
Results of post-irradiation examinations of mixed nitride pins with gas and liquid metal sub-layers	14
Development and validation of analysis code for spallation products behavior in LBE coolant system of ADS comparing with the distribution data in MEGAPIE spallation target	14
The effect of dry storage casks’ fuel loading on the heat load of final disposal canisters	14
Bubble behaviour and Critical heat flux on circular tubes during pool boiling process	14
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	14
National context of the recent Spanish research on nuclear fission technology	14
Editorial Board	14
Study on the subgroup method for the resonance self-shielding calculations in VITAS	13
Effect of maximum applied cyclic stress on fretting fatigue stress distribution of flat-on-flat modified 9Cr-1Mo steel contact: Finite element analysis	13
An educational simulation of a country’s electric power system	13
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	13
Time assessment of instrumentation survivability and severe accident guidelines application	13
Effect of hydrodynamic coupling on dynamic response of perforated tube	13
Methodology for phenomenological code assessment with integral test data	13
Foreword to “OUTCOMES AND ACHIEVEMENTS FROM RESEARCHES ORIENTING THE FUTURE IN NUCLEAR FISSION TECHNOLOGY: Denmark, Netherland, Sweden, Norway and Finland”	13
Validation of TRACE V5.0 for intermediate break in the cold leg of the reactor with passive emergency core cooling system via the ATLAS facility	13
Development and assessment of a reactor system prognosis model with physics-guided machine learning	13
MPOGen: A Python package to prepare few-group homogenized cross sections for core calculations by APOLLO3®	13
Development and Verification of a Computational Fluid Dynamics Model for a PWR-type Small Modular Reactor Subchannel	13
Thermal-Hydraulic comparative analysis of G-III + BWR and PWR passive safety features under Loss of coolant accident	13
Study on the dynamic response of reinforced concrete nuclear containment under the impact of large aircraft	13
TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system	12
Thermal safety characteristics analysis of helium xenon gas cooled small reactor system under LOCA accidents	12
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident	12
A new procedure for solving multigroup neutron diffusion eigenvalue problems	12
Batch Deterministic and Stochastic Petri nets Modeling for Reliability Quantification for Safety Critical Systems of Nuclear Power Plants	12
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	12
Experimental investigation on steam contact condensation in emergency makeup tank	12
Influence of embedment depth on floor response spectrum of SMR structure incorporating dynamic soil–structure interaction	12
Design and analysis on the HP-PHRS for small modular lead-bismuth fast reactor	12
Hydrogen distribution in a BWŔs RPV and Mark II drywell during the progression of a severe accident with and without emergency coolant injection	12
MELCOR integrated severe accident code application to safety assessment of high-temperature gas-cooled reactors	12
Flow rate measurement across the upper core structure of a sodium fast reactor using a scaled model and a simulant fluid	12
Liquid level monitoring and quenching front tracking for SMR rod bundle CHF tests under low pressure, low flow, high quality conditions	12
Economic aspects of nuclear fuel cycle closure on the basis of fast neutron reactors in the framework of “Proryv” project direction implementation	12
The effect of temperature variation on PCCS functional failure probability for AP1000 nuclear power plant	12
An experimental study of the thermal-hydraulics of a spent nuclear fuel pool under loss-of-cooling accident conditions. Part I: The MIDI facility and its main experimental results	12
Literature survey of droplet entrainment from water pools	12
A singular value decomposition entropy approach to instability analysis in BWR’s	12
Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly	12
Self-improving few-shot fault diagnosis for nuclear power plant based on man-machine collaboration	12
Multidimensional multiphysics simulations of the supercritical water-cooled fuel rod behaviors based on a new fuel performance code developed on the MOOSE platform	11
Measurement of corium surface tension using the maximum bubble pressure	11
A new dynamic rod worth measurement method based on the transient spatial factor	11
Mass transfer enhancement and flow field simulations for a Venturi bubble generator with multiple inlet tubes	11
Influence of soil structure interaction on G + 11 storied RC frame against unconfined surface blast loads	11
Progress in rod bundle CHF in the past 40 years	11
Fundamental experiment study on the fragmentation characteristics of molten lead jet direct contact with water	11
Supplementing fuel behaviour analyses via coupled Monte Carlo neutronics and fission product solution	11
Experiment design for the neutron irradiation of PM-HIP alloys for nuclear reactors	11
Generation modular reactors: A framework	11
Evaluation of flow-induced plate deflection for University of Missouri research reactor low-enriched uranium fuel element	11
Comparing physical protection strategies against insider threats using probabilistic risk assessment	11
Multidimensional modeling of fuel-cladding friction in an LWR fuel rod	11
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity	11
Analysis of Thermalhydraulics characteristics on constant and variable models for pressure tube radial expansion by using the ASSERT code in a CANDU6 channel	11
Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a VVER NPP. Part 2 – Modelling of the fission products transport	11
Evaluation of gas leaks from canisters by using a horizontal small-scale canister model	11
Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions	11
Direct contact condensation of steam jet in subcooled water: A review	11
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	11
Analysis of natural convection heat transfer and solidification within a corium simulant	11
Numerical studies on the effect of surface roughness on flow field and flow-induced vibration in the in-line tube bundle	11
Radiation shielding properties of heavy-weight concrete and heavy-weight geopolymer concrete incorporating nano-ZnS	11
Evaluation of RPV closure head penetration integrity considering fitting and residual stresses	11
Pressure drop experiment with externally and internally cooled annular fuel bundles	11
Numerical simulation of in-vessel steam explosion for China third-generation PWR	11
Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels	11
Investigation of the effects of the vane blades on the CAP1400 nuclear coolant pump’s performance based on a bionic strategy	11
Human reliability analysis of intelligent mine human–computer interaction based on improved SPAR-H	10
Shielding mass estimation model for gas-cooled space nuclear reactors	10
Validation process against late phase conditions of the passive autocatalytic recombiner simulation code PARUPM as a standalone tool using experimental data from REKO-3 and THAI facilities	10
Mechanical performance and self-sensing capability of an amorphous fiber-reinforced concrete for radioactive waste storage facilities	10
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases	10

Discussing the possibility of using thorium-based fuels as an alternative fuel to uranium dioxide fuel for APR-1400 reactor	10
Experimental investigation on the impact of different thermodynamic parameters on the depletion behavior of nuclear aerosols in the IN-EX facility	10
A neutronic evaluation of a thorium-based molten salt breeder reactor	10
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review	10
Effect of basket/rail gap on temperature prediction in the TN-32 cask under storage and drying conditions	10
Uncertainty and sensitivity analysis of a postulated severe accident in a generic German PWR with the system code AC2	10
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	10
Erratum to “Nuclear heat supply system for a small district heating reactor” [Nucl. Eng. Des. 426 (2024) 113389]	10
Experimental analyses and computational simulations of dilution events for an SMR pressurizer test facility	10
An open-source porous media modelling approach to investigate thermohydraulic features of compact printed circuit heat exchangers	10
Thermal conductivity of lead and bismuth-lead eutectic melts up to 1300 K	10
Analysis of the natural circulation flow map uncertainties in an integral small modular reactor	10
Study on potential burnable poison materials for a small modular block-type HTGR design using MgO-BeO as a composite-based moderators	10
Thermo-mechanical evaluation of UO2-SiC fuel rod in hypothetical accidents using COMSOL multiphysics	10
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	10
The feasibility study on development of porous ceramic composites for ion-exchanger	10
A comprehensive analysis of neutronic properties of annular dispersed particle fuel	9
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks	9
Quantification of uncertainties due to manufacturing tolerances using deterministic sampling methods	9
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow	9
Validation of SAS4A/SASSYS-1 for predicting steady-state single-phase natural circulation	9
Mechanistic critical heat flux prediction for in-vessel retention conditions	9
Structural, compositional and morphological characterization of Nd3+-substituted UO2 microspheres obtained by ICHTJ sol–gel technique	9
Dynamic characteristics analysis of RCP impeller based on fluid-thermal-solid coupling	9
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL	9
Validation of a MELCOR model of HTR-10 in normal operation and accident conditions	9
On structural finite element modeling strategies and their influence on the optimization of final constructability of reinforced concrete structures	9
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	9
Drift-flux parameter modeling of vertical downward gas–liquid two-phase flows for interfacial drag force formulation	9
Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator	9
Towards standardized nuclear reactors: Seismic isolation and the cost impact of the earthquake load case	9
Hydrogen risk assessment methodology for small containments using a commercial CFD code	9
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	9
Evaluation of a hybrid in-vessel retention strategy with ex-vessel cooling for APR1400 under extended station blackout conditions	9
Numerical study on the effect of CO2 on the heat transfer characteristics of steam condensation outside a vertical tube	9
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	9
Visualization experiments and a new correlation of critical heat flux in a narrow rectangular channel	9
Reactor design of UPR-1: A MW-level reactor for unmanned underwater vehicle propulsion using low-enriched uranium	9
Experimental research of heat transfer in heavy metallic layer under different top boundary conditions	9
Experimental study on eutectic reaction between lower head of reactor pressure vessel and molten pool using simulant materials	9
Modeling a generic Pebble Bed High-Temperature Gas-Cooled Reactor to perform load-following using Simulink	9
Impact of core power density on economics of a small integral PWR	9
Multi-physical coupling study of neutronics/thermal-hydraulics/material corrosion based on the unified coupling framework	9
Visualization of spacer grid effect on bubble behavior and CHF in a single-rod channel	9
Fuel cladding chemical interactions for MOX fuel in fast reactors	9
Effect of steam and oxygen starvation on severe accident progression with air ingress	9
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator	9
Evaluation framework for molten salt reactors and other new nuclear power reactor systems	9
Thermal analyses of high-power advanced thermoacoustic radioisotope power system for future space exploration missions	9
Knowledge representation to support EMDAP implementation in advanced reactor licensing applications	9
Mass transfer between a continuous oxide phase (U-O-Zr) and a steel droplet at liquid state: Potential impact on corium pool behaviour during in-vessel melt retention	9
Effect of tip injection on performance of highly loaded helium compressor in high-temperature gas-cooled reactor	9
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels	9
Coupled porous media approaches in sub-channel CFD	9
Seismic fragility analysis of nuclear shield building based on zoned structure	9
NEAMS IRP challenge problem 1: Flexible modeling for heat transfer for low-to-high Prandtl number fluids for applications in advanced reactors	9
Prediction of time-varying inner wall temperature of surge lines by a dynamic neural network	9
Validation of CFD RANS of an internally heated natural convection in a hemispherical geometry	9
Numerical investigation on transient aero-thermal characteristics of a labyrinth regulating valve for nuclear power plant	9
Study on a numerical homogenization method for printed circuit heat exchanger with hybrid mini-channels	9
Development and preliminary verification of a transient analysis code PANES-Tran for Nuclear thermal propulsion	9
MATLAB PDE toolbox for 2-D and 3-D neutron diffusion simulations	9
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives	9
Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application	9
Study on flow instability in natural circulation loop with parallel channels under moving condition	8
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	8
Evaluation of aerosol retention inside a steam generator under steam generator tube rupture accident conditions	8
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	8
Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor	8
Statistical characterization of the interfacial behavior captured by a novel image processing algorithm during the gas/liquid counter-current two-phase flow in a 1/3 scaled down of PWR hot leg	8
Settlement of combined piled raft foundation of a nuclear power plant in non-liquefiable and liquefiable soils	8
Codes and standards for ceramic composite core materials for High Temperature Reactor applications	8
A numerical study of the MRT-LBM for the shallow water equation in high Reynolds number flows: An application to real-world tsunami simulation	8
Study on pressure surge characteristics of reactor coolant pump shaft stuck accident condition based on wavelet analysis	8
Benchmarking of computational fluid dynamic models for bubbly flows	8
Numerical investigation on the Multi-Physics coupling characteristics of Lead-Bismuth reactor fuel assembly based on oxidation corrosion behaviors	8
State feedback control of HPR1000 average coolant temperature based on dominant pole	8
Heat transfer deterioration and visualized flow state of supercritical CO2 in a vertical non-circular channel	8
Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle	8
Conceptual design of megawatt-level mobile nuclear power system based on heat pipe cooled reactor	8
Influence of transverse vibration induced by fluid-structure interaction on pipeline strength	8
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	8
A viscoplastic approach to corium spreading during a severe nuclear accident	8
Numerical analyses of the CIRCE-THETIS facility by mean of STH and CFD codes	8
Analysis of the accuracy of residual heat removal in gen-IV reactors	8
Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses	8
A two-phase mathematical model to describe the dissolution of corium crust by molten steel	8
Comparison of lifetime assessments between ASME and RCC-MRx in liquid metal nuclear research reactors surfing from thermal striping	8
Model for determining rupture area in Zircaloy cladding under LOCA conditions	8
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	8
Scale analysis using FSA methodology for single-phase natural circulation in a simplified RCCS	8
Investigation on the effect of polydisperse spray droplets distribution on aerosol particles removal efficiency	8
Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film	8
Multi-physics coupling analysis on neutronics, thermal hydraulic and mechanics characteristics of a nuclear thermal propulsion reactor	8
Improving the safety of the high temperature gas-cooled reactor ‘HTTR’ based on Japan’s new regulatory requirements	8