Nuclear Engineering and Design

Article	Citations
Probability-based assessment of time-varying prestress losses in in-service containment structures	60
Study on heat transfer enhancement mechanism and performance evaluation of streamline spirally coiled tubes	49
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	45
Disruptive thermal-spectrum molten salt breeder reactor fuel cycle technologies	44
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	43
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	39
State feedback control of HPR1000 average coolant temperature based on dominant pole	36
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	35
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	33
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	32
National context of the recent Spanish research on nuclear fission technology	31
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	31
An educational simulation of a country’s electric power system	30
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	30
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	29
Development and assessment of a reactor system prognosis model with physics-guided machine learning	27
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	27
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	27
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	26
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics	25
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks	25
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	25
Implications of using nanoparticles on the performance and safety of nuclear systems	25
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	25
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	25

Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	24
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	24
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves	24
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	24
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels	23
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator	23
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	23
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	22
Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses	22
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	22
Performance evaluation of AHWR flux mapping system during normal operational scenarios	21
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	21
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	20
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	20
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	20
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	20
Effect of rolling motions on the single and two-phase pressure drop in annulus channel with helical-finned heater for floating nuclear reactor	20
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	20
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	20
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	19
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	19
Blast response of a scaled reinforced concrete structure with Two-Leaf cavity infill wall	19
Aircraft impact: Coupled dynamic simulations part 1: Modelling aspects	19
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	19
Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework	19
Dynamic modeling and simulation of the GAMA-AHR	19
A numerical study on metallic melt infiltration in porous media and the effect of solidification	19
A viscoplastic approach to corium spreading during a severe nuclear accident	18
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I	18
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	18
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	18
Assessment of wall heat flux partitioning model for two-phase CFD	17
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release	17
Implications of HALEU fuel on the design of SMRs and micro-reactors	17
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	17
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	17
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	17
Dynamic dose equivalent rate estimation in dismantling: Physic-informed surrogate modeling	17
Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core	17
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	17
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow	17
Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow	17
Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	17
Editorial Board	16
Multiphysics modeling approach for the analysis of noble metals deposition in the Molten Salt Fast Reactor	16
Conceptual design of small innovative helium-xenon cooled mobile nuclear power system	16
Sub-channel analysis of the influence of the ATF cladding corrosion on thermal hydraulic behaviors	16
Experimental study on the laser cutting process of the stainless steel hexagonal tube of fast reactor simulate assembly	16
Design of electrical feedouts for hard-core components in nuclear power plants	16
A novel approach for full-core mesh generation to enable high-fidelity thermal-hydraulic simulation of nuclear reactor engineering	16

Editorial Board	15
Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python	15
Optimization research of heat transfer coefficient prediction model for supercritical water based on Bayesian search algorithm	15
Effects of swirl intensity on interfacial and wall friction factors of annular flows in a vertical pipe	15
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	15
Experimental investigation of subcooled flow boiling characteristics of water in vertical helically coiled tubes	15
Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs	15
Editorial Board	15
Editorial Board	15
Editorial Board	15
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithm	15
Experience of mixed nitride uranium–plutonium fuel fabrication at the siberian chemical plant jsc site	15
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors	15
Online identification of trips caused by the external proton source in an ADS reactor	15
Modeling of atmospheric dispersion and radiological dose consequences for a hypothetical accident in the perspective of Rooppur Nuclear Power Plant (RNPP)	14
Development of a coarse-mesh subchannel CFD model for prediction of core thermal–hydraulics in natural circulation conditions	14
A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning	14
Advancing inherent safety in small modular reactors: A CFD-based analysis of the PIUS concept	14
Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite	14
Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh	14
Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR	14
Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark	14
Multi-physics simulation of a load rejection transient in a Pressurized water reactor. Comparison against experimental data, sensitivity and uncertainty study	14
Research on gaseous and liquid source term of tritium for pressurized water reactor	14
Radial reflector macroscopic cross sections preparation impact on the low neutron leakage core Beavrs	14
Development of core support barrel installation tool for a bypass flow reduction in nuclear reactor core	14
Establishing control points scheme and baseline measurements for environmental radioactivity monitoring: A case study of the nuclear Institute	14
Pre − test evaluation of a grid − spaced deformed fuel pin bundle	14
Study on flow-induced noise characteristics of multistage depressurization valve in the nuclear power plant	13
Investigation into different 1D/3D co-simulation methodologies applied to a natural circulation loop	13
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark	13
Thermal-pressure coupled loading of large-scale nuclear containment model	13
Neutron single-flow method for efficient production of Cf-252 in high-flux fast reactor	13
Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark	13
Towards strategic agenda for European nuclear education, training, and knowledge management	13
Validation of URANS and STRUCT-ε turbulence models for stratified sodium flow	13
Simulation of mixed convection heat transfer to liquid metals in vertical channels and pipes	13
Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system	13
Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator	13
Experimental investigations into the rocking response of graphite-block assemblies in a HTGR core under horizontal earthquake shaking	13
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark	13
An efficient method for input uncertainty propagation in CFD and the application to buoyancy-driven flows	13
A scoping study on debris bed formation from metallic melt coolant interactions	13
Phosphoric acid-activated metakaolin-based geopolymer: Optimizing P/A molar ratio to solidify Cs+ and Sr2+ in nuclear waste	13
Dynamics optimization of small branch pipes in nuclear power plants based on machine learning algorithms	13
Improving operational flexibility of the integrated pressurized water reactor with the MED-TVC desalination system by control logic systems in the off-design mode	13
Developing reference-based correlations for temperature distribution in VVER reactor using gene expression programming and single-heated channel approach	13
Application of REPAS to analyze the sump clogging issue following a LOCA and its impact on the reliability of the ECCS long-term core cooling function	13
Review of CHF experiment and prediction methods under motion condition	13
Thermal limits calculation for a BWR plant Simulator	13
Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly	12
EDITORIAL NOTE AT THE SPECIAL ISSUE: NEA/CSNI/WGAMA specialists meeting on nuclear thermal-hydraulics in water cooled reactors	12
Numerical analysis of developing laminar flows from a helical pipe to a straight pipe	12
Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundle	12
Validation of modeling scheme implementing MULTID component of MARS-KS code to predict shell-side pressure drop in shell-and-tube type heat exchangers	12
Comprehensive considerations for the co-decontamination and recycling of radioactively contaminated steels	12
Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo	12
New correlations for focusing effect evaluation of the light metal layer in the lower head of a nuclear reactor in case of severe accident	12
Numerical transfer towards unresolved morphology representation in the MultiMorph model	12
Numerical investigation of vapor bubble condensation in subcooled quiescent water	12
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics method	12
Experimental investigation of residence time and axial velocity of 6.0 cm graphite pebbles in a cold-flow pebble bed reactor using radioisotope-based technique	12
Study on the feasibility of dynamic rod worth measurement using fission chamber detector signal in HPR1000	12
Research on predicting the diffusion of radionuclide in complex building scenarios based on a hybrid deep learning model	12
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	12
Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactor	12
ANItA – A new Swedish national competence centre in new nuclear power technology	12
Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident	12
Risk reduction by means of FLEX strategies in pressurized water reactors	12
Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments	12
Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way	12
Evaluation of fully developed turbulent friction coefficient in polygonal section ducts and ducts with corner angle 0° by new characteristic lengths	12
Thermal-hydraulic analysis of the superheated steam supply system in NHR200-II using refined semi-2D modeling	12
High-Throughput falling ball viscometer for measuring High-Temperature molten salts	12
Flow-induced vibration of core barrel of small modular reactor: Fluctuating pressure	12
Flow instabilities in helical-coil steam generators for small modular reactors: A review	12
Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates	11
Experimental investigation on the effect of direct contact condensation regime on thermal stratification	11
Spark plasma sintering of fuel meats for U3O8 based dispersion fuels	11
Irregular pentagon loop for nuclear reactor natural circulation system test apparatus	11

Experimental study on thermally assisted sagging deflection and interaction of multiple coolant channels	11
Interfacial area transport modeling of air–water bubbly two-phase flows in inclined orientations	11
Novel methodology for functional design chain analysis of a nuclear power plant: A new built Finnish power plant case study	11
Study on graphite particle motion and impact in the helium circulator of HTGR	11
High-temperature oxidation of Zr-4 and Zr-1Nb-O alloys: Influencing factors, oxidation behaviors and mechanisms	11
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm	11
Study on influence of asymmetric safety injection on reactor pressure vessel integrity evaluation	11
Natural convection phenomena in a liquid metal pool due to relocated and heap of heat-generating core debris: Numerical study	11
Automatic recognition system for document digitization in nuclear power plants	11
Research on control strategies for rapid load decrease events in fluoride salt reactor-supercritical CO2 Brayton cycle systems	11
Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia	11
Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport	11
N-Euler mathematical modelling and numerical simulation of liquid–gas–solid flows	11
Parametric study of the influence of 135Xe build-up on required excess reactivity for load-following operations	11
Incorporation of uranium nitride fuel capability into the ENIGMA fuel performance code: Model development and validation	11
Assessment and predicting the axial power distribution effect on the thermal-mechanical parameters of the NuScale nuclear reactor core loaded with TVS-2 M fuel assemblies as well as axial Offset optim	11
Simulation of natural circulation cartridge loop experiments and application to molten salt reactors	11
Improved and extended correlation for critical heat flux in annuli	11
Similarity studies of buoyancy effects in impinging jets – Application to SFR core	11
Dynamic study of a steam Rankine cycle using CATHARE-3 system thermal-hydraulic code: Application to Superphenix fast reactor	11
New multi-fluid model of pool scrubbing in bubble rise region	11
CFD simulation plus uncertainty quantification of the mixing of two fluid with different density for the Cold-Leg mixing benchmark	11
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	11
Calculation of shutdown gamma distribution in the high temperature engineering test reactor	11
Structural optimization of gas-solid separator used in TMSR-SF based on computational fluid dynamics	11
Study on seismic safety evaluation of crossover pipeline connecting containment and turbine building in three-dimensional isolated nuclear power plant	11
Analysis on helium stratification erosion by vertical steam jet using the CUPID code	11
An assessment of radiation exposure of workers during decommissioning of reactor vessel at Kori #1 unit	11
Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system	11
Spanish research related to SMRs projects	11
Performance analysis and optimization of heat pipe-based radiator for space nuclear power system	11
Effects of liquid viscosity on interfacial and wall friction factors of swirling annular flows in a vertical pipe	11
Numerical simulation of operational transients in sodium-cooled fast reactors	11
Experimental and numerical investigation on dynamic characteristic of nozzle check valve and fluid-valve transient interaction	11
Development of singular value decomposition based solution scheme for a numerical simulation of multiphase flow	11
Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detection	10
Numerical investigation on steam condensation and heat transfer in an emergency condenser tube with the thermo-hydraulic system code ATHLET	10
Thermo-structural analysis of a dump nozzle for conducting hot liquid sodium	10
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	10
MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part II: Analysis of containment thermal-hydraulics and ex-vessel phenomena	10
Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-1: Spreading models, numerical solution methods and verifications	10
Energy loss analysis in cavitation flow of a continuous-resistance trim	10
Time-series forecasting of a typical PWR system response under Control Element Assembly withdrawal at full power	10
Molten salt reactor system dynamics in simulink and modelica, a code to code comparison	10
Scaling challenges in small modular reactor	10
Corrigendum to “A study of ammonia-hydrogen-electricity cogeneration coupled to a very high-temperature heat source” [Nucl. Eng. Design 414 (2023) 112585]>	10
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment	10
The possibility of utilizing novel cladding materials instead of zirconium in light water reactors	10
Outcomes and achievements from researches orienting the future in nuclear fission technology: NFT-18: Brazil, Peru and Bolivia	10
Analysis of the short Term-Station Blackout accident at the Peach Bottom Unit-2 reactor with ASTEC including the estimation of the radiological impact with JRODOS	10
Fuel depletion study of the molten salt demonstration reactor	10
Long term cooling safe shutdown performance analysis for SMART with passive safety system using MARS-KS	10
Investigation of the fission gas release and grain boundary percolation in oxide fuels: A COMSOL multiphysics-based study	10
Coupled neutronics and thermal-hydraulics transient simulation of a gas-cooled reactor in the aircraft nuclear propulsion system	10
Assessing turbulence models in PWR sub-channel geometry using q-DNS	10
Assuring fire safety in nuclear plants with international standards	10
Modeling of axial flow-induced vibrations of a BWR instrumentation guide tube experiment	10
Analysis of loss of flow without scram test in the FFTF reactor: Coupled 3D neutronics and thermal hydraulics analysis with DYN3D/ATHLET code system	10
Numerical study on the effects of tube inclination angle and heat conductive cover plate on freeze plug performance in molten salt reactors	10
Difference in accumulation of plutonium and curium isotopes formed in americium targets irradiated in Joyo and JMTR	10
TRISO fuel performance analysis: Uncertainty quantification toward optimization	10
Editorial Board	10
Construction schedule and cost risk for large and small light water reactors	10
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	10
Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod	10
Numerical appraisal of the role of heat transfer regimes on transient response of carbon dioxide based supercritical natural circulation loop during power upsurge	10
Kernel principle component analysis and random under sampling boost based fault diagnosis method and its application to a pressurized water reactor	10
Saudi Arabia's nuclear energy ambition and its compliance with IAEA guidelines for newcomers: An overview	9
Subgroup method for the high fidelity neutronics code SHARK and preliminary benchmarking	9
Design of a portable backup shutdown system for the high temperature gas cooled reactor	9
Iterative computed tomography reconstruction of void fraction in a fuel bundle on unstructured mesh	9
Impact of measurement error on deep neural networks for nuclear material accountancy	9
Erratum to “Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor” [Nucl. Eng. Design 403 (2023) 112163]	9
A modified mental workload model based on CREAM in the complex scenarios of advanced main control room in the nuclear power plant	9
A shape function approach for predicting deteriorated heat transfer to supercritical pressure fluids on account of a thermal entry length phenomenon	9
Flow Instabilities in boiling channels and their suppression methodologies—A review	9
Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-2: Special models and validations based on dry spreading experiments using molten oxide mixtures and prototy	9
Integrated aerosol-nuclide transport model for radiological source term characterization in HTGR primary loop	9
Development and validation of the MAVR-TA code for analyzing the release and transport of fission products during a severe accident at a nuclear power plant with VVER. Part 1 – Release of fission prod	9
Estimating degradation growth rate and time of component replacement from limited inspection data using mixed-effects modelling	9
Operational radioactive waste management strategies for small reactors in nuclear newcomer countries	9
SI: Best of HTR 2021	9
Application of data assimilation in searching better lattice-physics parameters of fuel assembly	9
Thermal hydraulic review of light water reactor based on subchannel code CTF	9
Hunting for the correct pressure drop in a scaled reactor pool: Effect of geometry, mesh resolution, turbulence model and mass flow	9
The porosity distribution in the HTTU annular packed bed of spheres	9
Adaptive second-order sliding-mode control for a pressurized water nuclear reactor in load following operation with Xenon oscillation suppression	9
Helium-air mixing in simulated reactor cavities of high temperature gas reactors	9
Fundamental and applied investigations of the liquid-metal cooled fast reactor thermal hydraulics (achieved results and further investigation issues)	9
Numerical investigation about radius ratio effect of helical tubes in the heat exchanger	9
Modified correlations for the Nusselt numbers at the boundaries of a bottom-heated molten metal layer in a stratified corium melt pool and an assessment of heat transfer conditions during a severe acc	9
Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX	9
Study on the effect of jet cross section shape on molten fuel fragmentation behavior with simulant experiments	9
RELAP5 validation for core makeup tank analysis based on separate effect tests	9
Data Adequacy by an Extended Analytic Hierarchy Process for Inverse Uncertainty Quantification in Nuclear Safety Analysis	9