Nuclear Engineering and Design

Article	Citations
A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications	131
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor	50
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor	41
Physics-informed reinforcement learning optimization of nuclear assembly design	37
Preliminary design of the suppressive containment system based on HPR1000	37
Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant	35
High-energy surface processing of zirconium alloys for fuel claddings of water-cooled nuclear reactors	34
ALFRED reactor coolant system design	34
Source localization on large-scale canisters for used nuclear fuel storage using optimal number of acoustic emission sensors	33
Burnable absorbers in nuclear reactors – A review	32
A new thermal analysis model with three heat conduction layers in the nuclear waste repository	31
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 – Results of severe accident analyses for unit 2	30
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) Phase 2 – Results of severe accident analyses for Unit 1	29
A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes	28
Review of molten salt reactor off-gas management considerations	28
Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)	25
Transfer learning with limited labeled data for fault diagnosis in nuclear power plants	25
Core power control of the ADS based on genetic algorithm tuning PID controller	25
Full core LOCA safety analysis for a PWR containing high burnup fuel	24
A review of recent advances in HTGR CFD and thermal fluid analysis	24
Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark	24
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives	23
Thermodynamic design and Off-design investigation of nuclear power supercritical CO2 recompression cycle	23
Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor	22
Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly	22

Heat transfer and flow characteristics of straight-type PCHEs with rectangular channels of different widths	22
Design and assessment of a molten chloride fast reactor	22
Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology	22
Progress in multiphase computational fluid dynamics	22
Fractal neutrons diffusion equation: Uniformization of heat and fuel burn-up in nuclear reactor	21
Fragility analysis of a prestressed concrete containment vessel subjected to internal pressure via the probability density evolution method	21
CFD investigation of the cold wall effect on CHF in a 5 × 5 rod bundle for PWRs	21
Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors	21
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3	21
Progress in two-phase flow modeling: Interfacial area transport	21
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	20
CFD simulation of an integrated PCM-based thermal energy storage within a nuclear power plant connected to a grid with constant or variable power demand	20
Fork-end heat pipe for passive air cooling of spent nuclear fuel pool	20
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	19
Progress in rod bundle CHF in the past 40 years	19
Evaluation of ASR in concrete using acoustic emission and deep learning	19
Direct contact condensation of steam jet in subcooled water: A review	19
Multi-nozzle spray cooling of a reactor pressure vessel steel plate for the application of ex-vessel cooling	18
Comprehensive parameter analyses on steam-air condensation at pressures up to 1.6 MPa	18
Analysis of two phase critical flow with a non-equilibrium model	18
Stochastic finite elements analysis of large concrete structures’ serviceability under thermo-hydro-mechanical loads – Case of nuclear containment buildings	18
Reactor power distribution detection and estimation via a stabilized gappy proper orthogonal decomposition method	18
Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe	18
FEA-aided investigation of the effective thermal conductivity in a medium with embedded spheres	17
Optimal and fast field reconstruction with reduced basis and limited observations: Application to reactor core online monitoring	17
High-fidelity numerical analysis of the damage and failure mechanisms of a prestressed concrete containment vessel under internal pressure	17
Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources	17
Design of an in-tank thermal neutron beam for PGNAA application at Isfahan MNSR	16
Investigation of the effects of surface wettability and surface roughness on nanoscale boiling process using molecular dynamics simulation	16
Numerical investigation on transient aero-thermal characteristics of a labyrinth regulating valve for nuclear power plant	16
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	16
Numerical simulation and experimental validation of flow characteristics for a butterfly check valve in small modular reactor	16
PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena	16
Three-dimensional numerical simulation of droplet formation by Rayleigh–Taylor instability in multiphase corium	16
Seismic isolation: A pathway to standardized advanced nuclear reactors	16
Progress in international best estimate plus uncertainty analysis methodologies	16
Thermal-fluid-structure analysis of fast pressure relief valve under severe nuclear accident	16
Experimental correlation for critical heat flux in helical coils	16
Analysis of the natural circulation flow map uncertainties in an integral small modular reactor	15
A fractional PID controller based on fractional point kinetic model and particle swarm optimization for power regulation of SMART reactor	15
BP neural network based reconstruction method for radiation field applications	15
Deep learning-based procedure compliance check system for nuclear power plant emergency operation	15
Experiments in free falling and downward cocurrent annular flows – Characterization of liquid films and interfacial waves	15
Progress in reflood thermal hydraulics studies in the past 40 years	15
Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout	15
Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials	14
A new coupled two-phase model for condensate film and steam condensation in the presence of air	14
Finite element analyses of the effect of weld overlay sizing on residual stresses of the dissimilar metal weld in PWRs	14
Conceptual design of a 3 MWth yttrium hydride moderated heat pipe cooled micro reactor	14
Impacts of constraints and uncertainties on projected amount of Hanford low-activity waste glasses	14

Benchmarking of computational fluid dynamic models for bubbly flows	14
Failure identification in a nuclear passive safety system by Monte Carlo simulation with adaptive Kriging	14
High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography	14
Implications of HALEU fuel on the design of SMRs and micro-reactors	14
Determination of the linear behavior of FC detectors in Isfahan MNSR using ex-core offline and online experiments	13
Total loss of flow benchmark in CIRCE-HERO integral test facility	13
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor	13
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters	13
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases	13
Numerical analysis of influence of geometry and operating parameters on Ledinegg and dynamic instability on supercritical water natural circulation loop	13
Seismic response of electrical equipment subjected to high–frequency ground motions	13
Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM	13
Density stratification breakup by a vertical jet: Experimental and numerical investigation on the effect of dynamic change of turbulent schmidt number	13
Thermal radiation, its effect on thermocouple measurements in the PANDA facility and how to compensate it	13
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	13
Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3	13
Feasibility study of nanomaterials synthesis at MNSR research reactor through design and construction of a gamma irradiation cell	13
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors	13
Effect of the flow approach angle on the dynamics of loosely-supported tube arrays	13
Pool boiling critical heat flux studies of accident tolerant fuel cladding materials	13
Experimental investigation of the pressure oscillations induced by subsonic steam jets under different vessel pressures	12
Attention-based time series analysis for data-driven anomaly detection in nuclear power plants	12
Literature survey of droplet entrainment from water pools	12
Numerical investigation of heat transfer enhancement in helically coiled specifically-shaped tube heat exchangers	12
Data-driven modeling of coarse mesh turbulence for reactor transient analysis using convolutional recurrent neural networks	12
Large eddy simulation on the heat transfer of supercritical pressure water in a circular pipe	12
Preliminary safety evaluation of a supercritical carbon dioxide Brayton cycle cooled reactor system under loss-of-flow accident	12
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	12
Towards standardized nuclear reactors: Seismic isolation and the cost impact of the earthquake load case	12
A review on optimization methods for nuclear reactor fuel reloading analysis	12
Phosphor thermometry for nuclear decommissioning and waste storage	12
Safety assessment of AP1000: Common transients, analysis codes and research gaps	12
Interaction of a diffusion barrier from the refractory metals with a zirconium alloy and a chrome coating of an accident tolerant fuel	12
Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors	12
Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)	12
An experimental study on the effects of task complexity and knowledge and experience level on SA, TSA and workload	12
Adaptive second-order sliding-mode control for a pressurized water nuclear reactor in load following operation with Xenon oscillation suppression	12
A machine learning strategy with restricted sliding windows for real-time assessment of accident conditions in nuclear power plants	11
Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactor	11
Multiple evaporator and condenser loop thermosyphon system for passive cooling of liquid-fuel molten salt nuclear reactors	11
Searching for the most optimum burnable absorbers (BAs) for AP-1000 from the neutronic, thermal-hydraulic, and solid mechanics points of view	11
Euler-Euler large eddy simulations of the gas–liquid flow in a cylindrical bubble column	11
CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000	11
Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR	11
Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1	11
Experimental research on convective heat transfer characteristics of molten salt in a pebble bed channel with internal heat source	11
A one-dimensional code of double-coupled passive residual heat removal system for the swimming pool-type low-temperature heating reactor	11
Conceptual core design and neutronics analysis for a space heat pipe reactor using a low enriched uranium fuel	11
Enhanced safety characteristics of SMART100 adopting passive safety systems	11
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam	11
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project	11
A dimensionless correlation to predict the onset of heat transfer deterioration of supercritical fluids in upward circular tubes	11
Nuclear graphite strength degradation under varying oxidizing conditions	11
Improved departure from nucleate boiling prediction in rod bundles using a physics-informed machine learning-aided framework	11
Multiobjective optimization of nuclear microreactor reactivity control system operation with swarm and evolutionary algorithms	11
Simulation of dynamic characteristics of NHR200-II fuel assembly	11
Commissioning of an MRI test facility for CFD-grade flow experiments in replicas of nuclear fuel assemblies and other reactor components	11
Validation of numerical models for seismic fluid-structure-interaction analysis of nuclear, safety-related equipment	11
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents	10
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I	10
Numerical simulation research on two-phase flow boiling heat transfer in helically coiled tube	10
Analysis of steam generator tube rupture accident for OPR 1000 nuclear power plant	10
Effect of inlet temperature on flow behavior and performance characteristics of supercritical carbon dioxide compressor	10
Analysis of particle shape effect on the discharging of non-spherical particles in HTR-10 reactor core	10
High-resolution thermal analysis of nuclear thermal propulsion fuel element using OpenFOAM	10
Physical design of an Atmospheric Neutron Irradiation Spectrometer at China Spallation Neutron Source	10
A review of the FLEX strategy for nuclear safety	10
A scoping study on debris bed formation from metallic melt coolant interactions	10
A framework analyzing system status and human activities: Illustrated using 2011 Fukushima nuclear power plant accident scenarios	10
Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies	10
Simulation of a NuScale core design with the CASL VERA code	10
Development of severe accident mitigation technology and analysis for SMART	10
Adventures in study of the pressure losses in wire-wrapped rod bundle arrays	10
SMART reactor core design optimization based on FCM fuel	10
Experimental study on steam plume shape characteristics for bevelled spray nozzles exhausting into quiescent water	10
The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2	10
AP1000 Passive Containment Cooling System study under LBLOCA conditions using the GOTHIC code	10
Computational fluid dynamics modelling of lead natural convection and solidification in a pool type geometry	10
Experiment design for the neutron irradiation of PM-HIP alloys for nuclear reactors	10
Using artificial intelligence to identify the success window of FLEX strategy under an extended station blackout	10

CFD study on the effect of various geometrical parameters of honeycomb type orifices on pressure drop and cavitation characteristics	10
Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions	10
Study of the ablation consecutive to jet impingement on a meltable solid – Application to SFR core-catcher	10
A Bayesian strategy for forecasting the leakage rate of concrete containment buildings – Application to nuclear containment buildings	10
Experimental and numerical investigation of non-uniform inflow on cavitation characteristics of reactor coolant pumps	10
Developed borated austenitic stainless steel alloys as nuclear reactor control rods	10
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC	10
Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor	9
Experimental study on the passive residual heat removal system of swimming pool-type low-temperature heating reactor	9
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident	9
A three-dimensional refined numerical simulation of cross-flow induced vibration mechanism in the tube bundle	9
Numerical study on the effect of CO2 on the heat transfer characteristics of steam condensation outside a vertical tube	9
Towards model order reduction for fluid-thermal analysis	9
Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor	9
Passive systems and nuclear thermal-hydraulics	9
Performance evaluation of DRACS system of molten salt reactors using a transient solidification model	9
Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle	9
Searching for managing the reactivity and increasing the fuel cycle life in the PWR by an untraditional method	9
Assessment of RELAP5/MOD3.2 for simulating density wave oscillation with a two-phase natural circulation test facility	9
Development of MERCURY for simulation of multidimensional fuel behavior for LOCA condition	9
Towards improving the predictive capability of computer simulations by integrating inverse Uncertainty Quantification and quantitative validation with Bayesian hypothesis testing	9
The non-uniform inflow structure of reactor coolant pump based on Laser Doppler Velocimetry	9
Code validation and application of hydrogen mitigation by passive autocatalytic recombiner in small modular reactor	9
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	9
Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor	9
Development of 3D transient neutronics and thermal-hydraulics coupling procedure and its application to a fuel pin analysis	9
Molten salt modelling in SPECTRA applied to MSRE	9
Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics	9
Semi-analytical modeling of the flow redistribution upstream from the mixing grids in a context of nuclear fuel assembly bow	9
Validation of the Griffin application for TREAT transient modeling and simulation	9
A coupled model of corrosion of the steam generator heat transfer tube	9
Scaling analysis and evaluation for the design of integral test facility of HPR1000 containment (PANGU)	9
Estimation of sensor measurement errors in reactor coolant systems using multi-sensor fusion	9
Subchannel analysis – Current practice and development for the future	9
Numerical characterization of heat transfer deterioration in supercritical natural circulation loop and role of loop inclination	9
Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments	9
Modeling of early stage droplet spreading based on numerical simulations	9
Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor	9
Effects of fluid properties on interfacial and wall friction factors under counter-current flow limitation in a vertical pipe with sharp-edged lower end	9
Diagnosing nuclear power plant pipe wall thinning due to flow accelerated corrosion using a passive, thermal non-destructive evaluation method: Feasibility assessment via numerical experiments	9
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release	9
Numerical simulation of bubble dynamics in subcooled flow boiling in a channel	9
Upgrading the PLINIUS platform toward smarter prototypic-corium experimental R&D	9
Simulation of jets induced by steam injection through multi-hole sparger using effective heat and momentum models	9
Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention	9
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	9
Behavior of moving droplet on inclined containment wall: Experiment and model validation	9
Study on strategy construction for dismantling and radioactive waste management at Fukushima Daiichi Nuclear Power Station	9
Shaking table experiments on 3/10 reduced-scale CAP1400 spent fuel storage rack considering the effect of fluid-structure interaction	8
Chemical Interactions of Molten Steel with (U-Zr-O) Corium: Main Outcomes of the CORDEB Program	8
Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network	8
The low-enriched uranium core design of a MW heat pipe cooled reactor	8
Saudi Arabia's nuclear energy ambition and its compliance with IAEA guidelines for newcomers: An overview	8
Numerical simulation of single-phase heat transfer and nucleate boiling of liquid sodium in narrow annulus channel similar to that of SFR fuel subchannel	8
Neutronic and thermohydraulic analysis of a SMR-PWR core with TRISO fuel based on a 2n multifactorial analysis	8
A numerical study of heat transfer enhancement by helically corrugated tubes in the intermediate heat exchanger of a very-high-temperature gas-cooled reactor	8
Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant	8
3D thermal hydraulic characteristics analysis of pool-type upper plenum for lead-cooled fast reactor with multi-scale coupling program	8
Topology optimization of an airfoil fin microchannel heat exchanger using artificial intelligence	8
Validation of a morphology adaptive multi-field two-fluid model considering counter-current stratified flow with interfacial turbulence damping	8
Recommended set of interfacial drag correlations for the two-phase flow under thermal–hydraulic conditions of a horizontal steam generator	8
In-depth analysis of mixing characteristics of stratified gases during spray operation in the TOSQAN Test 113 using OpenFOAM	8
Simplified criteria for a comparison of the accidental behaviour of Gen IV nuclear reactors and of PWRS	8
Nucleate boiling simulation using interface tracking method	8
Assessment of alternative radionuclides for use in a radioisotope thermoelectric generator	8
A new reduced order model to represent the creep induced fuel assembly bow in PWR cores	8
Numerical prediction of slug flow boiling heat transfer in the core-catcher cooling channel for severe accident mitigation in nuclear power plant	8
Monte Carlo method with SNBCK nongray gas model for thermal radiation in containment flows	8
Analysis of a LBLOCA with FLEX actuations in a PWR-W	8
A nonlinear soil-structure interaction analysis technique based on seismic isolation design response spectrum for seismically isolated nuclear structures with rigid basemat	8
Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor	8
Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13	8
Numerical investigation of vapor bubble condensation in subcooled quiescent water	8
Experimental and numerical investigation on heat transfer of supercritical water flowing upward in 2 × 2 rod bundles	8
An evaluation of selected friction factor correlations and results for the pressure drop through random and structured packed beds of uniform spheres	8
2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model	8
Settlement of combined piled raft foundation of a nuclear power plant in non-liquefiable and liquefiable soils	8
Evaluation of gas leaks from canisters by using a vertical small-scale canister model	8
Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data	8
Numerical simulation of micro-crack leakage on steam generator heat transfer tube	8
Three-dimensional numerical research on natural circulation characteristics of decay heat removal system in pool-type fast reactor CEFR	8
Experimental study of the features of the occurrence and development of condensation-induced water hammer in a horizontal pipe	8
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	8
Investigating the possible advantage of using LM bonded gap instead of helium in Ap-1000 nuclear power reactor	8
Structural MATerias research on parameters influencing the material properties of RPV steels for safe long-term operation of PWR NPPs	8
An experimental investigation on the characteristics of heat pipes with annular type composite wick structure	8
Bubble size distribution for bubbly-to-slug transition flow in narrow rectangular channel	8
Velocity field and flow redistribution in a ballooned 7×7 fuel bundle measured by magnetic resonance velocimetry	8
Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior	8
Heat transfer deterioration and visualized flow state of supercritical CO2 in a vertical non-circular channel	8
A simulation and machine learning informed diagnosis of the severe accidents	8
Development and application of a surrogate model for quick estimation of ex-vessel debris bed coolability	7
Thermal-hydraulic stability investigations of once through helically coiled steam generators for SMR applications	7
Thermal-hydraulic analysis of Al2O3 nanofluid as a coolant in Canadian supercritical water reactor by porous media approach	7
Machine learning based prediction of subcooled bubble condensation behavior, validation with experimental and numerical results	7