Nuclear Engineering and Design

Article	Citations
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	65
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	44
Assessment of wall heat flux partitioning model for two-phase CFD	44
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	38
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	35
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	34
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	33
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	32
National context of the recent Spanish research on nuclear fission technology	32
An educational simulation of a country’s electric power system	32
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	31
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	28
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	28
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	28
Implications of using nanoparticles on the performance and safety of nuclear systems	28
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	27
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	27
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	27
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	27
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	27
Performance evaluation of AHWR flux mapping system during normal operational scenarios	27
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	27
Effect of rolling motions on the single and two-phase pressure drop in annulus channel with helical-finned heater for floating nuclear reactor	26
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement	26
Dynamic modeling and simulation of the GAMA-AHR	25

A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	25
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	25
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	24
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	24
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	23
Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	23
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	23
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	23
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	22
Blast response of a scaled reinforced concrete structure with Two-Leaf cavity infill wall	22
Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework	22
Aircraft impact: Coupled dynamic simulations part 1: Modelling aspects	22
A numerical study on metallic melt infiltration in porous media and the effect of solidification	21
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	21
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	21
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	21
A viscoplastic approach to corium spreading during a severe nuclear accident	21
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics	21
Implications of HALEU fuel on the design of SMRs and micro-reactors	20
Static-dynamic coupled analysis of pumping station structure of a nuclear power plant using viscoelastic static-dynamic unified artificial boundary	20
Effect of brazing parameter and Zr-Cu-Ti powder filler metal on the microstructure and mechanical properties of SiC ceramic joints	20
Dissolution experiments with surrogate treated organic wastes immobilized by hot isostatic pressing	20
The actual constraints and consequences of the maneuvering operation of PWRs — An optimum seeking approach	20
High-fidelity forced convection simulations of the University of Wisconsin–Madison air-cooled reactor cavity cooling system	20
Development and assessment of a reactor system prognosis model with physics-guided machine learning	19
State feedback control of HPR1000 average coolant temperature based on dominant pole	19
Analysis of NERVA engine performance using point kinetics-based power balance modeling	19
Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core	19
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	19
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	19
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves	18
Disruptive thermal-spectrum molten salt breeder reactor fuel cycle technologies	18
Bubble generation and migration behavior in SGTR accident of LFR from a series of experiments	18
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	18
Probability-based assessment of time-varying prestress losses in in-service containment structures	18
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	18
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	18
Study on heat transfer enhancement mechanism and performance evaluation of streamline spirally coiled tubes	18
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	17
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	17
Sub-channel analysis of the influence of the ATF cladding corrosion on thermal hydraulic behaviors	17
Charging characteristics of typical alpha-emitting aerosols and their divergence from beta-emitters in nuclear emergency scenarios	17
Conceptual design of small innovative helium-xenon cooled mobile nuclear power system	17
Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow	17
Laser welding of PHWR end caps: A characterization study	17
Design of electrical feedouts for hard-core components in nuclear power plants	17
Study on flow-induced noise characteristics of multistage depressurization valve in the nuclear power plant	16
Experimental investigation of subcooled flow boiling characteristics of water in vertical helically coiled tubes	16
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	16
Editorial Board	16

New correlations for focusing effect evaluation of the light metal layer in the lower head of a nuclear reactor in case of severe accident	16
Simulation of mixed convection heat transfer to liquid metals in vertical channels and pipes	16
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithm	16
Validation of URANS and STRUCT-ε turbulence models for stratified sodium flow	16
Analysis of decay heat in spent nuclear fuel using serpent 2 simulations and Clab measurements	16
Multiphysics modeling approach for the analysis of noble metals deposition in the Molten Salt Fast Reactor	15
Experimental investigations into the rocking response of graphite-block assemblies in a HTGR core under horizontal earthquake shaking	15
Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python	15
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors	15
Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo	15
Editorial Board	15
Editorial Board	15
Thermal-pressure coupled loading of large-scale nuclear containment model	15
Effects of swirl intensity on interfacial and wall friction factors of annular flows in a vertical pipe	15
Simulation of flow field characteristics around longitudinally staggered variable-curvature helical coil bundles	15
Editorial Board	15
Editorial Board	15
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release	15
Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark	14
Research on gaseous and liquid source term of tritium for pressurized water reactor	14
Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR	14
Dynamic dose equivalent rate estimation in dismantling: Physic-informed surrogate modeling	14
A novel approach for full-core mesh generation to enable high-fidelity thermal-hydraulic simulation of nuclear reactor engineering	14
Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite	14
A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning	14
Radial reflector macroscopic cross sections preparation impact on the low neutron leakage core Beavrs	14
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	14
Towards strategic agenda for European nuclear education, training, and knowledge management	14
Dynamics optimization of small branch pipes in nuclear power plants based on machine learning algorithms	14
Development of core support barrel installation tool for a bypass flow reduction in nuclear reactor core	14
Optimization research of heat transfer coefficient prediction model for supercritical water based on Bayesian search algorithm	14
ANItA – A new Swedish national competence centre in new nuclear power technology	14
Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system	14
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark	14
Experimental study on the laser cutting process of the stainless steel hexagonal tube of fast reactor simulate assembly	13
Investigation into different 1D/3D co-simulation methodologies applied to a natural circulation loop	13
A data-driven reduced-order modeling approach for state estimation in IPWR forced-to-natural circulation transitions	13
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	13
Comprehensive safety analysis and advanced design features of the SMART100 small modular reactor	13
Thermal limits calculation for a BWR plant Simulator	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
Risk reduction by means of FLEX strategies in pressurized water reactors	13
Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly	13
EDITORIAL NOTE AT THE SPECIAL ISSUE: NEA/CSNI/WGAMA specialists meeting on nuclear thermal-hydraulics in water cooled reactors	13
Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh	13
CATHARE calculation of the tests conducted on the ELSMOR passive heat removal system	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
Establishing control points scheme and baseline measurements for environmental radioactivity monitoring: A case study of the nuclear Institute	13
Development of STEAM code: a steam generator tube-level three-dimensional thermal–hydraulic analysis platform	13
A multi-level sensitivity analysis for the model parameters of the main steam system in nuclear power plants	13
Numerical investigation of vapor bubble condensation in subcooled quiescent water	13
Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactor	13
Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident	13
Developing a fragility assessment procedure for fault displacement based on SSHAC level 2 process	13
An efficient method for input uncertainty propagation in CFD and the application to buoyancy-driven flows	13
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark	13
Editorial Board	13
Development of a coarse-mesh subchannel CFD model for prediction of core thermal–hydraulics in natural circulation conditions	12
Review of CHF experiment and prediction methods under motion condition	12
Phosphoric acid-activated metakaolin-based geopolymer: Optimizing P/A molar ratio to solidify Cs+ and Sr2+ in nuclear waste	12
Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates	12
Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundle	12
High-Throughput falling ball viscometer for measuring High-Temperature molten salts	12
Flow instabilities in helical-coil steam generators for small modular reactors: A review	12
Numerical analysis of developing laminar flows from a helical pipe to a straight pipe	12
Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator	12
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics method	12
Numerical transfer towards unresolved morphology representation in the MultiMorph model	12
U&S analyses in a BWR NPP LB-Loca transient with ATF	12
Multi-physics simulation of a load rejection transient in a Pressurized water reactor. Comparison against experimental data, sensitivity and uncertainty study	12
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	12
Study on the feasibility of dynamic rod worth measurement using fission chamber detector signal in HPR1000	12
Thermal-hydraulic analysis of the superheated steam supply system in NHR200-II using refined semi-2D modeling	12
Evaluation of fully developed turbulent friction coefficient in polygonal section ducts and ducts with corner angle 0° by new characteristic lengths	12
Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments	12
Developing reference-based correlations for temperature distribution in VVER reactor using gene expression programming and single-heated channel approach	12
Modeling of atmospheric dispersion and radiological dose consequences for a hypothetical accident in the perspective of Rooppur Nuclear Power Plant (RNPP)	12
Flow-induced vibration of core barrel of small modular reactor: Fluctuating pressure	12
Pre − test evaluation of a grid − spaced deformed fuel pin bundle	12

Advancing inherent safety in small modular reactors: A CFD-based analysis of the PIUS concept	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
Automatic recognition system for document digitization in nuclear power plants	12
Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs	12
Improving operational flexibility of the integrated pressurized water reactor with the MED-TVC desalination system by control logic systems in the off-design mode	12
Demonstration of the inherent safety feature of HTGRs through the loss-of-forced-cooling test in the HTTR	12
Interfacial area transport modeling of air–water bubbly two-phase flows in inclined orientations	11
Comprehensive considerations for the co-decontamination and recycling of radioactively contaminated steels	11
Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod	11
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	11
Study on influence of asymmetric safety injection on reactor pressure vessel integrity evaluation	11
Corrigendum to “A study of ammonia-hydrogen-electricity cogeneration coupled to a very high-temperature heat source” [Nucl. Eng. Design 414 (2023) 112585]>	11
Spark plasma sintering of fuel meats for U3O8 based dispersion fuels	11
Investigation of the fission gas release and grain boundary percolation in oxide fuels: A COMSOL multiphysics-based study	11
Novel methodology for functional design chain analysis of a nuclear power plant: A new built Finnish power plant case study	11
Structural optimization of gas-solid separator used in TMSR-SF based on computational fluid dynamics	11
Numerical appraisal of the role of heat transfer regimes on transient response of carbon dioxide based supercritical natural circulation loop during power upsurge	11
Experimental and numerical investigation on dynamic characteristic of nozzle check valve and fluid-valve transient interaction	11
Long term cooling safe shutdown performance analysis for SMART with passive safety system using MARS-KS	11
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	11
Incorporation of uranium nitride fuel capability into the ENIGMA fuel performance code: Model development and validation	11
An automated unsupervised anomaly detection framework for DCS controller logs in nuclear power plants	11
Dynamic study of a steam Rankine cycle using CATHARE-3 system thermal-hydraulic code: Application to Superphenix fast reactor	11
Scaling challenges in small modular reactor	11
Assessing turbulence models in PWR sub-channel geometry using q-DNS	11
Experimental investigation on the effect of direct contact condensation regime on thermal stratification	11
Calculation of shutdown gamma distribution in the high temperature engineering test reactor	11
Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way	11
Study on seismic safety evaluation of crossover pipeline connecting containment and turbine building in three-dimensional isolated nuclear power plant	11
Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-1: Spreading models, numerical solution methods and verifications	11
TRISO fuel performance analysis: Uncertainty quantification toward optimization	11
Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system	11
Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detection	11
Research on control strategies for rapid load decrease events in fluoride salt reactor-supercritical CO2 Brayton cycle systems	11
Construction schedule and cost risk for large and small light water reactors	11
Fuel depletion study of the molten salt demonstration reactor	11
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm	11
Kernel principle component analysis and random under sampling boost based fault diagnosis method and its application to a pressurized water reactor	11
Numerical simulation of operational transients in sodium-cooled fast reactors	11
Thermo-structural analysis of a dump nozzle for conducting hot liquid sodium	10
Analysis on helium stratification erosion by vertical steam jet using the CUPID code	10
Study on the thermal hydraulic performance of a separated structure shell-and-tube steam generator under various operating conditions	10
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	10
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	10
Radiation damage simulation of reactor pressure vessel material: A multi-scale approach	10
Time-series forecasting of a typical PWR system response under Control Element Assembly withdrawal at full power	10
High-temperature oxidation of Zr-4 and Zr-1Nb-O alloys: Influencing factors, oxidation behaviors and mechanisms	10
Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport	10
Improved and extended correlation for critical heat flux in annuli	10
Parametric study of the influence of 135Xe build-up on required excess reactivity for load-following operations	10
Irregular pentagon loop for nuclear reactor natural circulation system test apparatus	10
Coupled neutronics and thermal-hydraulics transient simulation of a gas-cooled reactor in the aircraft nuclear propulsion system	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
Numerical investigation on steam condensation and heat transfer in an emergency condenser tube with the thermo-hydraulic system code ATHLET	10
Spanish research related to SMRs projects	10
Assuring fire safety in nuclear plants with international standards	10
Energy loss analysis in cavitation flow of a continuous-resistance trim	10
Assessment of radiation dose and environmental impact from design basis accidents at the BAEC TRIGA research reactor	10
New multi-fluid model of pool scrubbing in bubble rise region	10
Similarity studies of buoyancy effects in impinging jets – Application to SFR core	10
Developing a digital twin framework for remotely monitoring nuclear reactor facilities	10
Critical heat flux detection and temperature profile measurement with OFDR in a carbon dioxide cooled tube at high subcritical pressures	10
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment	10
N-Euler mathematical modelling and numerical simulation of liquid–gas–solid flows	10
Numerical study on the effects of tube inclination angle and heat conductive cover plate on freeze plug performance in molten salt reactors	10
Editorial Board	10
Effects of liquid viscosity on interfacial and wall friction factors of swirling annular flows in a vertical pipe	10
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	10
Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia	10
An assessment of radiation exposure of workers during decommissioning of reactor vessel at Kori #1 unit	10
A comparative study of oxide scales formed on Alloy 690 in deaerated supercritical water and supercritical CO2 at 600 °C	10
Simulation of natural circulation cartridge loop experiments and application to molten salt reactors	10
Modeling of axial flow-induced vibrations of a BWR instrumentation guide tube experiment	10
Performance analysis and optimization of heat pipe-based radiator for space nuclear power system	10
Research on predicting the diffusion of radionuclide in complex building scenarios based on a hybrid deep learning model	10
Molten salt reactor system dynamics in simulink and modelica, a code to code comparison	10
Difference in accumulation of plutonium and curium isotopes formed in americium targets irradiated in Joyo and JMTR	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	9
Resumption of water capsule reactivity-initiated accident testing at TREAT	9
A cyclic-track decomposition method for 3D MOC neutron transport simulation	9
Site response analysis: Uncertain motions propagating through uncertain elastoplastic soil	9
Modelling of a passive hydraulic lock concept for the mitigation transfer tubes in a SFR core	9
Safety considerations related to boron redistribution during Loss-of-Coolant-Accident initiated beyond design basis events for the NuScale power module	9
The large-break LOCA uncertainty analysis in a VVER-1000 reactor using TRACE and DAKOTA	9
Validation of the STEG code using experiments on Two-Phase flow across horizontal tube bundles	9
Numerical analysis on flow distribution of nuclear reactor core inlet under ocean conditions	9
Neutronics simulation of China Experimental Fast Reactor start-up tests using FARCOB and ERANOS 2.1 code systems	9
Experimental study on boundary-conditioned hydration impact on bentonite gas permeability with supporting modeling	9
Steady-state and power transient critical heat flux experiments of FeCrAl and Zircaloy claddings under saturated pool boiling	9
Experimental study on fuel depressurization and its effect on dispersion	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
Investigation of dog-boning & fishtailing defects in plate type dispersion fuel Rolling: Insights from finite element analysis and defect minimization techniques	9
Cementitious mortar for Intermediate and Low-Level Radioactive waste confinement: Matrix optimization and leaching	9
Test program and numerical studies on reinforced concrete slabs impacted by liquid-filled missiles	9