Nuclear Engineering and Design

Article	Citations
A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications	108
Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor	43
Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor	36
Kairos power thermal hydraulics research and development	34
Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant	32
Transformational Challenge Reactor preconceptual core design studies	30
Physics-informed reinforcement learning optimization of nuclear assembly design	30
A new thermal analysis model with three heat conduction layers in the nuclear waste repository	30
Effect of vent size on explosion overpressure and flame behavior during vented hydrogen–air mixture deflagrations	30
ALFRED reactor coolant system design	30
Source localization on large-scale canisters for used nuclear fuel storage using optimal number of acoustic emission sensors	29
Review of molten salt reactor off-gas management considerations	26
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	26
Impact of nuclear energy on fossil fuel substitution	25
Design of a hundred-kilowatt level integrated gas-cooled space nuclear reactor for deep space application	25
Preliminary design of the suppressive containment system based on HPR1000	25
High-energy surface processing of zirconium alloys for fuel claddings of water-cooled nuclear reactors	24
Integral LOCA fragmentation test on high-burnup fuel	23
Thermodynamic design and Off-design investigation of nuclear power supercritical CO2 recompression cycle	23
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	23
RNN-Based online anomaly detection in nuclear reactors for highly imbalanced datasets with uncertainty	22
A comprehensive survey of inverse uncertainty quantification of physical model parameters in nuclear system thermal–hydraulics codes	21
A review of recent advances in HTGR CFD and thermal fluid analysis	21
Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology	21
Core power control of the ADS based on genetic algorithm tuning PID controller	21

CFD investigation of the cold wall effect on CHF in a 5 × 5 rod bundle for PWRs	20
Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly	20
Transfer learning with limited labeled data for fault diagnosis in nuclear power plants	20
Numerical optimization of a finned tube bundle heat exchanger arrangement for passive spent fuel pool cooling to ambient air	20
Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)	20
Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor	20
CFD simulation on the flow characteristics in the PWR lower plenum with different internal structures	19
Fractal neutrons diffusion equation: Uniformization of heat and fuel burn-up in nuclear reactor	19
Progress in two-phase flow modeling: Interfacial area transport	19
High-temperature mechanical behaviors of diffusion-welded Alloy 617	19
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	19
Ageing and air leakage assessment of a nuclear reactor containment mock-up: VERCORS 2nd benchmark	19
Heat transfer and flow characteristics of straight-type PCHEs with rectangular channels of different widths	19
Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors	19
Design and assessment of a molten chloride fast reactor	18
Comprehensive parameter analyses on steam-air condensation at pressures up to 1.6 MPa	18
Nonlinear vibrations of a nuclear fuel rod supported by spacer grids	18
Modeling and simulation of a High Flux Isotope Reactor representative core model for updated performance and safety basis assessments	18
Forced convection heat transfer of molten Salts: A review	18
Liquid metal thermal hydraulics: State-of-the-art and future perspectives	18
Stochastic finite elements analysis of large concrete structures’ serviceability under thermo-hydro-mechanical loads – Case of nuclear containment buildings	18
Burnable absorbers in nuclear reactors – A review	18
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	17
Nonlinear vibrations of a 3 × 3 reduced scale PWR fuel assembly supported by spacer grids	17
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives	17
Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe	17
Integral molten salt reactor neutron physics study using Monte Carlo N-particle code	17
Progress in multiphase computational fluid dynamics	17
Direct contact condensation of steam jet in subcooled water: A review	17
Multiphysics for nuclear energy applications using a cohesive computational framework	16
Evaluation of ASR in concrete using acoustic emission and deep learning	16
Fork-end heat pipe for passive air cooling of spent nuclear fuel pool	16
Fragility analysis of a prestressed concrete containment vessel subjected to internal pressure via the probability density evolution method	16
Analysis of two phase critical flow with a non-equilibrium model	16
Full core LOCA safety analysis for a PWR containing high burnup fuel	16
Three-dimensional numerical simulation of droplet formation by Rayleigh–Taylor instability in multiphase corium	16
Reactor power distribution detection and estimation via a stabilized gappy proper orthogonal decomposition method	16
Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor core	16
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems	15
Application of differential evolution algorithm for fuel loading optimization of the DNRR research reactor	15
Preliminary evaluation of ALFRED revised concept under station blackout	15
Optimal and fast field reconstruction with reduced basis and limited observations: Application to reactor core online monitoring	15
Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out	15
High-fidelity numerical analysis of the damage and failure mechanisms of a prestressed concrete containment vessel under internal pressure	15
Numerical investigation on transient aero-thermal characteristics of a labyrinth regulating valve for nuclear power plant	15
Multi-nozzle spray cooling of a reactor pressure vessel steel plate for the application of ex-vessel cooling	15
Progress in international best estimate plus uncertainty analysis methodologies	15
Experimental investigation of density stratification behavior during outer surface cooling of a containment vessel with the CIGMA facility	15
Seismic isolation: A pathway to standardized advanced nuclear reactors	14
A new coupled two-phase model for condensate film and steam condensation in the presence of air	14

High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography	14
Numerical study of flow-induced vibration of fuel rods	14
Experimental correlation for critical heat flux in helical coils	14
Deep learning-based procedure compliance check system for nuclear power plant emergency operation	14
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	14
Wall heat transfer in the inverted annular film boiling regime	14
Numerical simulation and experimental validation of flow characteristics for a butterfly check valve in small modular reactor	14
NECP-hydra: A high-performance parallel S code for core-analysis and shielding calculation	14
Finite element analyses of the effect of weld overlay sizing on residual stresses of the dissimilar metal weld in PWRs	14
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	14
FEA-aided investigation of the effective thermal conductivity in a medium with embedded spheres	14
Modified turbulent Prandtl number model for helium–xenon gas mixture with low Prandtl number	14
Development and validation of a new module in the ATHROC for simulation of aerosol particles removal by spray in containment	14
Low enriched nuclear thermal propulsion neutronic, thermal hydraulic, and system design space analysis	14
Assessment of the design effects on the structural performance of the Printed Circuit Heat Exchanger under very high temperature condition	14
Progress in rod bundle CHF in the past 40 years	14
Analysis of the natural circulation flow map uncertainties in an integral small modular reactor	14
Numerical analysis of influence of geometry and operating parameters on Ledinegg and dynamic instability on supercritical water natural circulation loop	13
Failure identification in a nuclear passive safety system by Monte Carlo simulation with adaptive Kriging	13
Thermal-fluid-structure analysis of fast pressure relief valve under severe nuclear accident	13
Benchmarking of computational fluid dynamic models for bubbly flows	13
Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials	13
Wall resolved large eddy simulation of reactor core flows with the spectral element method	13
A collaborative effort towards the accurate prediction of turbulent flow and heat transfer in low-Prandtl number fluids	13
Design of an in-tank thermal neutron beam for PGNAA application at Isfahan MNSR	13
PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena	13
Simulation of operational conditions of HX-HERO in the CIRCE facility with CFD/STH coupled codes	13
Assessment of near-term fuel screening and qualification needs for nuclear thermal propulsion systems	12
Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3	12
A fractional PID controller based on fractional point kinetic model and particle swarm optimization for power regulation of SMART reactor	12
BP neural network based reconstruction method for radiation field applications	12
Numerical investigation on the effect of transversal fluid field deformation on heat transfer in a rod bundle with mixing vanes	12
Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors	12
Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources	12
A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics	12
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters	12
Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout	12
Progress in reflood thermal hydraulics studies in the past 40 years	12
Application of genetic algorithm for optimization of control rods positioning in a fast breeder reactor core	12
Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM	12
Effect of temperature difference on the thermal mixing phenomenon in a T-junction under inflow pulsation	12
Experiments in free falling and downward cocurrent annular flows – Characterization of liquid films and interfacial waves	12
Impacts of constraints and uncertainties on projected amount of Hanford low-activity waste glasses	12
Initial demonstration of automated fuel performance modeling with 1977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases	12
Measurement of Zircaloy-4 cladding tube deformation using a three-dimensional digital image correlation system with internal transient heating and pressurization	12
Neutronic characteristics and feasibility analysis of micro-heterogeneous duplex ThO2-UO2 fuel pin in PWR	11
Data-driven modeling of coarse mesh turbulence for reactor transient analysis using convolutional recurrent neural networks	11
Basic design analysis of a heavy water-cooled thorium breeder reactor	11
Safety assessment of AP1000: Common transients, analysis codes and research gaps	11
Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor	11
Density stratification breakup by a vertical jet: Experimental and numerical investigation on the effect of dynamic change of turbulent schmidt number	11
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	11
Total loss of flow benchmark in CIRCE-HERO integral test facility	11
Improved departure from nucleate boiling prediction in rod bundles using a physics-informed machine learning-aided framework	11
Thermal radiation, its effect on thermocouple measurements in the PANDA facility and how to compensate it	11
Commissioning of an MRI test facility for CFD-grade flow experiments in replicas of nuclear fuel assemblies and other reactor components	11
CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000	11
Towards standardized nuclear reactors: Seismic isolation and the cost impact of the earthquake load case	11
Large eddy simulation on the heat transfer of supercritical pressure water in a circular pipe	11
Assessment of RANS models in predicting mixing flow induced by split-type vanes in rod bundle	11
Influence of PT-CT contact on PHWR fuel channel thermal behaviour under accident condition – An experimental study	11
Evaluation of energy and impulse generated by superheated steam bubble collapse in subcooled water	11
Multiple evaporator and condenser loop thermosyphon system for passive cooling of liquid-fuel molten salt nuclear reactors	10
Neutronics and thermal-hydraulics coupling analysis using the FLUENT code and the RELAP5-3D code for a molten salt fast reactor	10
Influence of the packing structure on the flow through packed beds with small cylinder diameter to particle diameter ratios	10
Simulation of dynamic characteristics of NHR200-II fuel assembly	10
Numerical simulation of temperature heterogeneity inside the AP1000 upper plenum and hot leg	10
Literature survey of droplet entrainment from water pools	10
A machine learning strategy with restricted sliding windows for real-time assessment of accident conditions in nuclear power plants	10
Design of NDI-SMC based robust hybrid nonlinear controller for load following operation in pressurized water reactor	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
Enhanced safety characteristics of SMART100 adopting passive safety systems	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
Feasibility study of nanomaterials synthesis at MNSR research reactor through design and construction of a gamma irradiation cell	10
Euler-Euler large eddy simulations of the gas–liquid flow in a cylindrical bubble column	10
A framework analyzing system status and human activities: Illustrated using 2011 Fukushima nuclear power plant accident scenarios	10
An experimental study on the effects of task complexity and knowledge and experience level on SA, TSA and workload	10
CFD study on the effect of various geometrical parameters of honeycomb type orifices on pressure drop and cavitation characteristics	10
Analysis of particle shape effect on the discharging of non-spherical particles in HTR-10 reactor core	10

Experimental characterization of boiling two-phase flow structures under BWR core operating conditions	10
Investigation of the effects of surface wettability and surface roughness on nanoscale boiling process using molecular dynamics simulation	10
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC	10
A Co-ordinated Control Methodology for Rapid Load-Following Operation of a Pressurized Water Reactor Based Small Modular Reactor	10
Seismic response of electrical equipment subjected to high–frequency ground motions	10
Pool boiling critical heat flux studies of accident tolerant fuel cladding materials	10
Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding	10
Phosphor thermometry for nuclear decommissioning and waste storage	10
Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions	9
The advanced reactor technologies (art) graphite R&D program	9
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors	9
Development and verification of code IMPC-Depletion for nuclide depletion calculation	9
A coupled model of corrosion of the steam generator heat transfer tube	9
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam	9
Preliminary safety evaluation of a supercritical carbon dioxide Brayton cycle cooled reactor system under loss-of-flow accident	9
Numerical investigation of heat transfer enhancement in helically coiled specifically-shaped tube heat exchangers	9
Computational fluid dynamics modelling of lead natural convection and solidification in a pool type geometry	9
Towards improving the predictive capability of computer simulations by integrating inverse Uncertainty Quantification and quantitative validation with Bayesian hypothesis testing	9
Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)	9
Modeling of early stage droplet spreading based on numerical simulations	9
Simulation and application of Bi-directional corrugated honeycomb aluminum as filling material for impact limiter of nuclear spent fuel transport cask	9
Simulation of a NuScale core design with the CASL VERA code	9
Development of severe accident mitigation technology and analysis for SMART	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
SMART reactor core design optimization based on FCM fuel	9
Upgrading the PLINIUS platform toward smarter prototypic-corium experimental R&D	9
Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle	9
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project	9
Determination of the linear behavior of FC detectors in Isfahan MNSR using ex-core offline and online experiments	9
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident	9
System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents	9
Method to determine nuclear accident release category via environmental monitoring data based on a neural network	9
The explosions at Fukushima Daiichi Unit 3 and Unit 4 and implications on the evaluation of 1F3 accident	9
Flow morphology and heat transfer analysis during high-pressure steam condensation in an inclined tube part I: Experimental investigations	9
Droplet impaction in nuclear installations and safety analysis: Phenomena, findings and approaches	9
Experimental study on thermo-mechanical deformation of PHWR channel at elevated temperature	9
Experimental research on convective heat transfer characteristics of molten salt in a pebble bed channel with internal heat source	9
Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux	9
Demonstration of the STRUCT turbulence model for mesh consistent resolution of unsteady thermal mixing in a T-junction	9
Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention	9
Development of MERCURY for simulation of multidimensional fuel behavior for LOCA condition	9
Analysis of fission product distribution and composition in the TRISO layers of AGR-2 fuel	9
Study on strategy construction for dismantling and radioactive waste management at Fukushima Daiichi Nuclear Power Station	9
Validation of the Griffin application for TREAT transient modeling and simulation	9
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I	9
Effect of velocity and pressure on performance of a full-scale SG steam separator package	9
Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies	9
Effect of the flow approach angle on the dynamics of loosely-supported tube arrays	9
Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1	9
Conceptual design of a 3 MWth yttrium hydride moderated heat pipe cooled micro reactor	9
Conceptual core design and neutronics analysis for a space heat pipe reactor using a low enriched uranium fuel	8
Semi-analytical modeling of the flow redistribution upstream from the mixing grids in a context of nuclear fuel assembly bow	8
Experimental study on steam plume shape characteristics for bevelled spray nozzles exhausting into quiescent water	8
Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario	8
Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor	8
A scoping study on debris bed formation from metallic melt coolant interactions	8
Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor	8
3D thermal hydraulic characteristics analysis of pool-type upper plenum for lead-cooled fast reactor with multi-scale coupling program	8
Numerical simulation research on two-phase flow boiling heat transfer in helically coiled tube	8
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	8
Nuclear graphite strength degradation under varying oxidizing conditions	8
Experiment design for the neutron irradiation of PM-HIP alloys for nuclear reactors	8
Effect of inlet temperature on flow behavior and performance characteristics of supercritical carbon dioxide compressor	8
Numerical simulation of bubble dynamics in subcooled flow boiling in a channel	8
Efficient global sensitivity analysis of structural vibration for a nuclear reactor system subject to nonstationary loading	8
Design and thermal-hydraulic evaluation of the finned-tube type sodium-to-air heat exchanger in sodium test facility	8
Experimental investigation of the pressure oscillations induced by subsonic steam jets under different vessel pressures	8
Influences of fabrication tolerance on thermal hydraulic performance of HTGR helical tube once through steam generator	8
A review on optimization methods for nuclear reactor fuel reloading analysis	8
Validation of numerical models for seismic fluid-structure-interaction analysis of nuclear, safety-related equipment	8
Experimental and numerical investigation on heat transfer of supercritical water flowing upward in 2 × 2 rod bundles	8
Subchannel analysis – Current practice and development for the future	8
A simplified model for the quaternary U-Zr-Fe-O system in the miscibility gap	8
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	8
A new reduced order model to represent the creep induced fuel assembly bow in PWR cores	8
In-depth analysis of mixing characteristics of stratified gases during spray operation in the TOSQAN Test 113 using OpenFOAM	8
Adaptive second-order sliding-mode control for a pressurized water nuclear reactor in load following operation with Xenon oscillation suppression	8
A one-dimensional code of double-coupled passive residual heat removal system for the swimming pool-type low-temperature heating reactor	8
High-resolution thermal analysis of nuclear thermal propulsion fuel element using OpenFOAM	8
Searching for the most optimum burnable absorbers (BAs) for AP-1000 from the neutronic, thermal-hydraulic, and solid mechanics points of view	8
Multiobjective optimization of nuclear microreactor reactivity control system operation with swarm and evolutionary algorithms	8
Characterization of crack propagation of Incoloy 800H by the combination of DIC and XFEM	8
Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors	8
2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model	8
Reliability improvements of corrosion-resistant equipment for thermochemical water splitting hydrogen production iodine-sulfur process	8
A fast reactor transmutation system for 6 LLFP nuclides	8
Scaling analysis and evaluation for the design of integral test facility of HPR1000 containment (PANGU)	8
Towards model order reduction for fluid-thermal analysis	8
Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient	8
Nucleate boiling simulation using interface tracking method	8
Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments	8
CFD modelling of buoyancy driven flows in enclosures with relevance to nuclear reactor safety	8
A summary of fission-product-transport phenomena during SGTR severe accidents	8
Experimental study of the features of the occurrence and development of condensation-induced water hammer in a horizontal pipe	8
Development and application of a surrogate model for quick estimation of ex-vessel debris bed coolability	7