Nuclear Engineering and Design

Article	Citations
Coupled porous media approaches in sub-channel CFD	50
Bilinear hysteresis in PWR fuel assemblies under quasi-static loading: Theoretical modeling and experimental validation	44
A comprehensive analysis of neutronic properties of annular dispersed particle fuel	39
Acoustic field study of ultrasonic transducers for nuclear pipelines using an improved Gaussian beam method	37
Development and preliminary validation of a mechanistic multiscale model for fuel-cladding chemical interaction in metallic nuclear fuels	35
Study on the subgroup method for the resonance self-shielding calculations in VITAS	34
Effect of hydrodynamic coupling on dynamic response of perforated tube	33
Analysis of Thermalhydraulics characteristics on constant and variable models for pressure tube radial expansion by using the ASSERT code in a CANDU6 channel	32
Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations	30
Visualization of spacer grid effect on bubble behavior and CHF in a single-rod channel	28
Experimental study of the transient boiling phenomenon on a vertically placed ribbon	26
Neutronic characteristics of the VVER-1000 fuel assembly with mechanical spectral shift regulation	25
Visualization experiments and a new correlation of critical heat flux in a narrow rectangular channel	25
An inversion model for burnup history of spent fuels in pebble bed HTGR based on optimization algorithm	24
Fuel element microreactor integrating a square UO2 fuel rod with an internal heat pipe	24
Human reliability analysis of intelligent mine human–computer interaction based on improved SPAR-H	24
Application of an open-set recognition method for detecting untrained accident scenarios in a nuclear power plant accident diagnosis model	24
Thermal conductivity of lead and bismuth-lead eutectic melts up to 1300 K	24
Burnable absorbers in nuclear reactors – A review	22
Virtual reality simulation of radioactive waste relocation with dynamic dose rate visualization	22
Editorial Board	22
The non-uniform inflow structure of reactor coolant pump based on Laser Doppler Velocimetry	22
Editorial Board	21
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	21
Modeling and simulation of the radiolytic deuterium and oxygen generation in heavy water reactors	21

Editorial Board	21
Conceptual design and analysis of a combined passive cooling system for both reactor and spent fuel of the pool-vessel reactor system	21
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	21
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation	20
Safety analysis and evaluation of transport and storage container for very Low-Level liquid radioactive waste	19
Reactor design of UPR-1: A MW-level reactor for unmanned underwater vehicle propulsion using low-enriched uranium	19
Analysis and evaluation of the irradiated dimensional and volume change behavior of nuclear graphites	19
Time averaged tomographic measurements before and after dryout in a simplified BWR subchannel geometry	19
Depressurization of nuclear power plants through a silica gel-based system	19
MATLAB PDE toolbox for 2-D and 3-D neutron diffusion simulations	19
Scale analysis using FSA methodology for single-phase natural circulation in a simplified RCCS	18
Conceptual design of megawatt-level mobile nuclear power system based on heat pipe cooled reactor	18
Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle	17
Steam flows in concrete cracks: Thermal behaviour	17
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	17
Editorial Board	17
Numerical analyses of the CIRCE-THETIS facility by mean of STH and CFD codes	17
Error in bubble velocity measurement using 4-sensor void probe due to interface deformation	16
On the importance of consistency of multiple-level modeling of multiphase flow in reactor systems	16
A simple correlation to estimate agglomerated debris formation based on experiments of melt jet-breakup using a metallic melt	16
Editorial Board	16
Development of the reactor core isolation cooling system model for the extended station black-out accident	16
Study on flow instability in natural circulation loop with parallel channels under moving condition	16
Drift-flux parameter modeling of vertical downward gas–liquid two-phase flows for interfacial drag force formulation	16
Nuclear reactor Thermal-Hydraulics Special and prospective topical areas	16
Experimental study on condensation heat transfer characteristics in C-shaped tube under rolling conditions	15
A framework analyzing system status and human activities: Illustrated using 2011 Fukushima nuclear power plant accident scenarios	15
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	15
Effects of inclined condition on LOCA for a small offshore reactor with OTSG	15
A two-phase mathematical model to describe the dissolution of corium crust by molten steel	15
An estimation method for near real-time accountancy of partitioned materials during chopper operations of used metallic nuclear fuel processing	15
Experimental investigation and modeling of flow boiling in microchannel heat exchangers for integral steam generator applications	14
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	14
Editorial Board	14
Autonomous search investigation for radioactive leaked source based on an updated infotaxis method during nuclear emergency rescue	14
Experimental research of heat transfer in heavy metallic layer under different top boundary conditions	14
Core physical conceptual design of small reactor for unmanned underwater vehicle	14
Acceleration calibration method for the drop test of radioactive package based on the rebound of specimen	14
Codes and standards for ceramic composite core materials for High Temperature Reactor applications	14
Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code	14
Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film	14
Investigation of reactivity control strategies for a micro-transportable gas-cooled thermal reactor	14
Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds number	14
Uncertainty and disturbance estimator based spatial power control of advanced heavy water reactor	14
Editorial Board	14
Start-up behavior and the ignition limit of passive hydrogen recombiners with various catalytic elements	14
Experimental and theoretical study on formation of interfacial waves on liquid film of annular two-phase flow	14
A machine learning diagnosis of the severe accident progression	14
Development and validation of Loss of Coolant Accident (LOCA) simulation capability in the ENIGMA fuel performance code for zirconium-based cladding materials	14
Foreword	13

Modeling and comparative analysis of changeover of homogeneous and heterogeneous core of BN-1200 reactor to equilibrium mode	13
Fundamental experiment study on the fragmentation characteristics of molten lead jet direct contact with water	13
Experimental investigation on distribution of boric acid in a vertical 1 × 2 rod array channel	13
Numerical analysis of a small-scale novel vortex tower integrated with heat source for Nuclear Application	13
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	13
Optimization of preparation process and study on the properties and microstructures of nuclear natural graphite powder for HTR pebble fuel elements	13
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	13
A standard capsule design for structural material testing in the Advanced Test Reactor	13
Design of an ultra-compact imaging chamber and radiation beamstop for a neutron radiography system employing particle transport	12
Mechanism and risk assessment of baffle-jetting-induced vibrations in fuel rods	12
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL	12
Predictive maturity of non-linear concrete constitutive models for impact simulation	12
Editorial Board	12
A newly proposed data assimilation framework to enhance predictions for reflood tests	12
Quantification of uncertainties due to manufacturing tolerances using deterministic sampling methods	12
Dissolution of contaminant Zr-DBP and corrosion of stainless steel by dissolved solution	12
Power transient critical heat flux in a narrow rectangular channel under downward flow	12
Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR	12
Core design: Review & perspectives in Spain	12
Mechanistic critical heat flux prediction for in-vessel retention conditions	11
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator	11
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels	11
Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25	11
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	11
Modeling the behavior of reinforced concrete slabs subjected to impact	11
Editorial Board	11
Theoretical analysis about model simplifications and boundary conditions on two-phase flow instability of parallel heated tube systems	11
Bubble behaviour and Critical heat flux on circular tubes during pool boiling process	11
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres	11
Numerical simulations of nuclear fuel reprocessing plant subjected to the free drop impact of spent fuel cask and fuel assembly	11
Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application	11
Thermal analyses of high-power advanced thermoacoustic radioisotope power system for future space exploration missions	11
On structural finite element modeling strategies and their influence on the optimization of final constructability of reinforced concrete structures	11
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	10
Effects of fuel relocation on fuel performance and evaluation of safety margin to 10CFR50.46c ECCS acceptance criteria in APR1400 plant	10
Theoretical analysis of the flow stability of HTGR supercritical steam generators using dimensionless numbers	10
A comprehensive analysis of thermal–hydraulic signatures in neutron noise of WWER-type reactors	10
Development process of FPGA based technology for control rod drive systems of experimental power reactor	10
Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor	10
SOURCE a computer code for fission-product partitioning and release from fuel	10
A numerical study of the MRT-LBM for the shallow water equation in high Reynolds number flows: An application to real-world tsunami simulation	10
Uncertainty quantification (UQ) for CFD simulation of OECD-NEA cold leg mixing benchmark	10
Status of benchmark exercises in the frame of the NUGENIA QUESA project	10
Improving the reactor safety aspects by the implementation of (Th-U233-Pu) fuel in a PWR assembly	10
Safety evaluation of Multiple Steam Generator Tube rupture accident using the best estimate plus uncertainty approach	10
A viscoplastic approach to corium spreading during a severe nuclear accident	10
Editorial Board	10
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	10
2D and 3D numerical investigations of sodium boiling in sodium cooled fast reactor with MOX fuel and low sodium void reactivity effect during unprotected loss of flow accidents	10
Editorial Board	10
Comparison and optimization of heat transfer models in reactor channel under the rolling condition	10
Effect of steam and oxygen starvation on severe accident progression with air ingress	10
Evaluation of aerosol retention inside a steam generator under steam generator tube rupture accident conditions	10
Influence of thermal effects on the cavitation of orifices in nuclear power plants	10
The progress on the 3D whole-core neutronics calculation of PANGU code	10
Experimental study on flow rate distortion of natural circulation reduced-height scaling	10
Sensitivity analysis for characterizing the impact of HNGD model on the prediction of hydrogen redistribution in Zircaloy cladding using BISON code	10
TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system	9
An algorithm for solving the equations of the Nodal Expansion Method in parallel using GPU	9
Secondary system modeling and primary system coupled simulation using MARS-KS	9
Achievements of recent research on severe accidents at CEA/IRESNE in support of future nuclear fission technology	9
Effect of maximum applied cyclic stress on fretting fatigue stress distribution of flat-on-flat modified 9Cr-1Mo steel contact: Finite element analysis	9
A neutronic evaluation of a thorium-based molten salt breeder reactor	9
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	9
Comparison of accelerated and non-accelerated post-LOCA simulation	9
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions	9
Development and Verification of a Computational Fluid Dynamics Model for a PWR-type Small Modular Reactor Subchannel	9
Open self-paced introductory course in nuclear engineering – How to guarantee student learning	9
An improved model based on real gas state equation and fog formation for condensation heat and mass transfer	9
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	9
Study on the dynamic response of reinforced concrete nuclear containment under the impact of large aircraft	9
The effect of dry storage casks’ fuel loading on the heat load of final disposal canisters	9
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	9
Flame wrinkling factor in quiescent hydrogen-air mixtures	9
Foreword to “OUTCOMES AND ACHIEVEMENTS FROM RESEARCHES ORIENTING THE FUTURE IN NUCLEAR FISSION TECHNOLOGY: Denmark, Netherland, Sweden, Norway and Finland”	9
A detailed experimental evaluation of gas –Liquid film attributes in a horizontal rectangular duct by Planar Laser-Induced fluorescence (PLIF) approach	9
Critical configuration of a SMR based on CAREM 25 using the SERPENT code	9
Structural, compositional and morphological characterization of Nd3+-substituted UO2 microspheres obtained by ICHTJ sol–gel technique	9
Multi-physics coupling analysis on neutronics, thermal hydraulic and mechanics characteristics of a nuclear thermal propulsion reactor	9
Methodology for phenomenological code assessment with integral test data	9

In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	9
Computational fluid dynamics modelling of lead natural convection and solidification in a pool type geometry	9
Implications of using nanoparticles on the performance and safety of nuclear systems	9
MPOGen: A Python package to prepare few-group homogenized cross sections for core calculations by APOLLO3®	9
Thermal-Hydraulic comparative analysis of G-III + BWR and PWR passive safety features under Loss of coolant accident	9
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	9
Study on tritium permeation behavior in primary and second circuits of the hydrogen production system by methane steam reforming using HTGR	9
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	9
An open-source porous media modelling approach to investigate thermohydraulic features of compact printed circuit heat exchangers	9
National context of the recent Spanish research on nuclear fission technology	9
A proposed refueling scheme for the modular pebble bed reactor	9
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	9
An educational simulation of a country’s electric power system	9
Miniature DC electromagnetic pumps of molten lead and sodium to support development of Gen-IV nuclear reactors	9
Time assessment of instrumentation survivability and severe accident guidelines application	9
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow	8
Literature survey of droplet entrainment from water pools	8
Comparing physical protection strategies against insider threats using probabilistic risk assessment	8
Numerical study on the effect of co-current gas flow on the falling film flow characteristics outside the horizontal tube	8
Liquid level monitoring and quenching front tracking for SMR rod bundle CHF tests under low pressure, low flow, high quality conditions	8
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	8
Risk-informed design of advanced nuclear reactor: A target unavailability approach	8
Self-improving few-shot fault diagnosis for nuclear power plant based on man-machine collaboration	8
Oxide characteristics of 90Nb-10Zr alloy corroded under different water chemistry conditions	8
Design and analysis on the HP-PHRS for small modular lead-bismuth fast reactor	8
Thermal safety characteristics analysis of helium xenon gas cooled small reactor system under LOCA accidents	8
Machine learning based prediction of subcooled bubble condensation behavior, validation with experimental and numerical results	8
Batch Deterministic and Stochastic Petri nets Modeling for Reliability Quantification for Safety Critical Systems of Nuclear Power Plants	8
Experimental investigation on steam contact condensation in emergency makeup tank	8
Flow rate measurement across the upper core structure of a sodium fast reactor using a scaled model and a simulant fluid	8
MELCOR integrated severe accident code application to safety assessment of high-temperature gas-cooled reactors	8
Study on a numerical homogenization method for printed circuit heat exchanger with hybrid mini-channels	8
Radiation shielding properties of heavy-weight concrete and heavy-weight geopolymer concrete incorporating nano-ZnS	8
Demonstration of a random sampling approach to uncertainty propagation for generic pebble-bed fluoride-salt-cooled high temperature reactor (gFHR)	8
Research on approaches to automatic modeling of discrete ordinate programs based on CAD model	8
Benchmark exercise on ELSMOR passive heat removal system	8
Numerical investigation of transient hydrodynamic properties during reflood with early power termination using the COSINE subchannel code	8
Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses	8
The effect of temperature variation on PCCS functional failure probability for AP1000 nuclear power plant	8
The nuclear research infrastructures open access scheme of the Joint Research Centre (JRC) at the European Commission – Contributions to education, training, mobility and scientific excellence	8
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	8
A new procedure for solving multigroup neutron diffusion eigenvalue problems	8
A study of filtering performance of a new microfluidic inertial impactor for small-scale nuclear reactors	8
Effect of basket/rail gap on temperature prediction in the TN-32 cask under storage and drying conditions	8
Evaluation of RPV closure head penetration integrity considering fitting and residual stresses	8
Influence of soil structure interaction on G + 11 storied RC frame against unconfined surface blast loads	8
Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly	8
Analysis of a test facility for transients in a supercritical water-cooled reactor using dynamic system scaling methodology	8
Effect of surface nanocrystallization on thermomechanical fatigue behavior of Ti-2Al-2.5Zr alloy tube	8
Hydrogen distribution in a BWŔs RPV and Mark II drywell during the progression of a severe accident with and without emergency coolant injection	8
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	8
Influence of embedment depth on floor response spectrum of SMR structure incorporating dynamic soil–structure interaction	8
A singular value decomposition entropy approach to instability analysis in BWR’s	8
Development and assessment of a reactor system prognosis model with physics-guided machine learning	8
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	7
Application of deterministic sampling methods for uncertainty quantification in manufacturing tolerances in neutron physics	7
Numerical investigation on transient aero-thermal characteristics of a labyrinth regulating valve for nuclear power plant	7
Measurement of corium surface tension using the maximum bubble pressure	7
Assessment of wall heat flux partitioning model for two-phase CFD	7
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	7
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	7
Towards standardized nuclear reactors: Seismic isolation and the cost impact of the earthquake load case	7
Thermal Modeling of an eVinci™-like heat pipe microreactor using OpenFOAM	7
Economic aspects of nuclear fuel cycle closure on the basis of fast neutron reactors in the framework of “Proryv” project direction implementation	7
Lead/lead-alloy as a corrosion-resistant outer layer packaging material for high level nuclear waste disposal	7
Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator	7
Study on potential burnable poison materials for a small modular block-type HTGR design using MgO-BeO as a composite-based moderators	7
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	7
An explicit expression of empirical parameter in ZBS model for predicting pebble bed effective thermal conductivity	7
Improving the safety of the high temperature gas-cooled reactor ‘HTTR’ based on Japan’s new regulatory requirements	7
Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis	7
Evaluation of flow-induced plate deflection for University of Missouri research reactor low-enriched uranium fuel element	7
Fragility analysis of a prestressed concrete containment vessel subjected to internal pressure via the probability density evolution method	7
Analysis of natural convection heat transfer and solidification within a corium simulant	7
Analysis of the coherence between FIV acceleration and flow velocity in a square array tube bank with P/D = 1.26	7
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	7
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	7
A compact Monte Carlo method for the calculation of k∞ and its application in analysis of (n,xn) reactions	7
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases	7
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	7
Erratum to “Nuclear heat supply system for a small district heating reactor” [Nucl. Eng. Des. 426 (2024) 113389]	7
Thermo-mechanical evaluation of UO2-SiC fuel rod in hypothetical accidents using COMSOL multiphysics	7
Mechanical performance and self-sensing capability of an amorphous fiber-reinforced concrete for radioactive waste storage facilities	7
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	7
Theoretical modeling of the boiling annular-mist flow in vertical channels	7
Model for determining rupture area in Zircaloy cladding under LOCA conditions	7
Impact of core power density on economics of a small integral PWR	7
Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	7
Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor	7
A new dynamic rod worth measurement method based on the transient spatial factor	7
Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions	7
Consideration of change over time in nuclear accident consequence assessment to support optimization of long-term remediation strategy	7
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	7
Uncertainty and sensitivity analysis of a postulated severe accident in a generic German PWR with the system code AC2	7
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	7