Nuclear Engineering and Design

Article	Citations
Implications of HALEU fuel on the design of SMRs and micro-reactors	60
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	55
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	44
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	41
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	39
A numerical study on metallic melt infiltration in porous media and the effect of solidification	38
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	38
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	38
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	34
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves	32
Performance evaluation of AHWR flux mapping system during normal operational scenarios	31
Development and assessment of a reactor system prognosis model with physics-guided machine learning	31
Measurement of corium surface tension using the maximum bubble pressure	29
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	28
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	27
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	27
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	27
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	26
Editorial Board	25
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation	24
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	23
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	23
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks	23
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	23
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator	22

Simulation and optimization of a conical type swirl-vane separator in nuclear SG	22
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels	22
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	22
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow	22
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	22
State feedback control of HPR1000 average coolant temperature based on dominant pole	22
National context of the recent Spanish research on nuclear fission technology	21
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	21
An educational simulation of a country’s electric power system	21
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	21
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	20
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	20
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	20
Depressurization of nuclear power plants through a silica gel-based system	20
A viscoplastic approach to corium spreading during a severe nuclear accident	20
Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses	19
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	19
Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	19
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL	19
Quantification of uncertainties due to manufacturing tolerances using deterministic sampling methods	19
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	18
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	18
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	18
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	18
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	18
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	18
Literature survey of droplet entrainment from water pools	17
Coupled porous media approaches in sub-channel CFD	17
Assessment of wall heat flux partitioning model for two-phase CFD	17
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	16
Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core	16
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	16
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	16
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	16
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics	16
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	16
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	16
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I	16
Implications of using nanoparticles on the performance and safety of nuclear systems	16
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	16
EDITORIAL NOTE AT THE SPECIAL ISSUE: NEA/CSNI/WGAMA specialists meeting on nuclear thermal-hydraulics in water cooled reactors	15
Experience of mixed nitride uranium–plutonium fuel fabrication at the siberian chemical plant jsc site	15
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark	15
Editorial Board	15
Editorial Board	15
Investigation on the hydraulic process of inertia tank in the case of pump trips	15
Editorial Board	15
Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python	15
Investigation into different 1D/3D co-simulation methodologies applied to a natural circulation loop	15
Review of research using analogy concept for thermal hydraulic and severe accident experiments	15

Editorial Board	15
Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident	15
Research on gaseous and liquid source term of tritium for pressurized water reactor	15
Editorial Board	15
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark	14
Numerical transfer towards unresolved morphology representation in the MultiMorph model	14
Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system	14
Risk reduction by means of FLEX strategies in pressurized water reactors	14
Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow	14
Radial reflector macroscopic cross sections preparation impact on the low neutron leakage core Beavrs	14
Experimental and numerical study of 19-pin disassembled fuel channel under severe accident condition	14
Establishing control points scheme and baseline measurements for environmental radioactivity monitoring: A case study of the nuclear Institute	14
Effects of swirl intensity on interfacial and wall friction factors of annular flows in a vertical pipe	14
Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo	14
Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator	14
Sub-channel analysis of the influence of the ATF cladding corrosion on thermal hydraulic behaviors	14
Development of core support barrel installation tool for a bypass flow reduction in nuclear reactor core	14
Numerical analysis of developing laminar flows from a helical pipe to a straight pipe	14
Study on flow-induced noise characteristics of multistage depressurization valve in the nuclear power plant	14
Online identification of trips caused by the external proton source in an ADS reactor	14
Monitoring of helium gas leakage from canister storing spent nuclear fuel: Radiological consequences and management	13
Dynamics optimization of small branch pipes in nuclear power plants based on machine learning algorithms	13
Towards strategic agenda for European nuclear education, training, and knowledge management	13
Development of a coarse-mesh subchannel CFD model for prediction of core thermal–hydraulics in natural circulation conditions	13
ANItA – A new Swedish national competence centre in new nuclear power technology	13
A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning	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
Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactor	13
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors	13
Validation of numerical models for seismic fluid-structure-interaction analysis of nuclear, safety-related equipment	13
Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh	13
Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR	13
Developing reference-based correlations for temperature distribution in VVER reactor using gene expression programming and single-heated channel approach	13
Numerical investigation of vapor bubble condensation in subcooled quiescent water	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
Eigenvalue sensitivity and nuclear data uncertainty analysis for the Moroccan TRIGA Mark II research reactor using SCALE6.2 and MCNP6.2	13
Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs	12
Experimental study on the laser cutting process of the stainless steel hexagonal tube of fast reactor simulate assembly	12
Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark	12
Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly	12
Thermal limits calculation for a BWR plant Simulator	12
A novel approach for full-core mesh generation to enable high-fidelity thermal-hydraulic simulation of nuclear reactor engineering	12
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	12
Validation of URANS and STRUCT-ε turbulence models for stratified sodium flow	12
Simulation of mixed convection heat transfer to liquid metals in vertical channels and pipes	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
An efficient method for input uncertainty propagation in CFD and the application to buoyancy-driven flows	12
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release	12
Modeling of atmospheric dispersion and radiological dose consequences for a hypothetical accident in the perspective of Rooppur Nuclear Power Plant (RNPP)	12
Flow instabilities in helical-coil steam generators for small modular reactors: A review	12
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithm	12
Neutron single-flow method for efficient production of Cf-252 in high-flux fast reactor	12
Experimental investigation of subcooled flow boiling characteristics of water in vertical helically coiled tubes	12
Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark	12
Dynamic dose equivalent rate estimation in dismantling: Physic-informed surrogate modeling	12
A scoping study on debris bed formation from metallic melt coolant interactions	12
Long term cooling safe shutdown performance analysis for SMART with passive safety system using MARS-KS	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
New correlations for focusing effect evaluation of the light metal layer in the lower head of a nuclear reactor in case of severe accident	11
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics method	11
New multi-fluid model of pool scrubbing in bubble rise region	11
Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia	11
Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates	11
Assuring fire safety in nuclear plants with international standards	11
Molten salt reactor system dynamics in simulink and modelica, a code to code comparison	11
CFD simulation plus uncertainty quantification of the mixing of two fluid with different density for the Cold-Leg mixing benchmark	11
Corrigendum to “Integral LOCA fragmentation test on high-burnup fuel” [Nucl. Eng. Design (2020) 367 110811, ISN 0029-5493]	11
Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-1: Spreading models, numerical solution methods and verifications	11
Evaluation of fully developed turbulent friction coefficient in polygonal section ducts and ducts with corner angle 0° by new characteristic lengths	11
Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments	11
Phosphoric acid-activated metakaolin-based geopolymer: Optimizing P/A molar ratio to solidify Cs+ and Sr2+ in nuclear waste	11
Scaling challenges in small modular reactor	11
Experimental study on thermally assisted sagging deflection and interaction of multiple coolant channels	11
Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system	11
Novel methodology for functional design chain analysis of a nuclear power plant: A new built Finnish power plant case study	11
Numerical simulation of operational transients in sodium-cooled fast reactors	11
Irregular pentagon loop for nuclear reactor natural circulation system test apparatus	11
Construction schedule and cost risk for large and small light water reactors	11
Comprehensive considerations for the co-decontamination and recycling of radioactively contaminated steels	11
Review of CHF experiment and prediction methods under motion condition	11

Flow-induced vibration of core barrel of small modular reactor: Fluctuating pressure	11
An assessment of radiation exposure of workers during decommissioning of reactor vessel at Kori #1 unit	11
Simulation of natural circulation cartridge loop experiments and application to molten salt reactors	11
Detailed thermal modelling of the ALLEGRO ceramic assembly	11
Spanish research related to SMRs projects	11
Coupled neutronics and thermal-hydraulics transient simulation of a gas-cooled reactor in the aircraft nuclear propulsion system	11
Kernel principle component analysis and random under sampling boost based fault diagnosis method and its application to a pressurized water reactor	11
Dynamic study of a steam Rankine cycle using CATHARE-3 system thermal-hydraulic code: Application to Superphenix fast reactor	10
Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport	10
Similarity studies of buoyancy effects in impinging jets – Application to SFR core	10
Assessing turbulence models in PWR sub-channel geometry using q-DNS	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 on graphite particle motion and impact in the helium circulator of HTGR	10
Study on influence of asymmetric safety injection on reactor pressure vessel integrity evaluation	10
Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detection	10
Natural convection phenomena in a liquid metal pool due to relocated and heap of heat-generating core debris: Numerical study	10
Parametric study of the influence of 135Xe build-up on required excess reactivity for load-following operations	10
Effects of liquid viscosity on interfacial and wall friction factors of swirling annular flows in a vertical pipe	10
Analysis on helium stratification erosion by vertical steam jet using the CUPID code	10
N-Euler mathematical modelling and numerical simulation of liquid–gas–solid flows	10
Development of singular value decomposition based solution scheme for a numerical simulation of multiphase flow	10
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	10
Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod	10
TRISO fuel performance analysis: Uncertainty quantification toward optimization	10
Validation of modeling scheme implementing MULTID component of MARS-KS code to predict shell-side pressure drop in shell-and-tube type heat exchangers	10
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment	10
Incorporation of uranium nitride fuel capability into the ENIGMA fuel performance code: Model development and validation	10
High-Throughput falling ball viscometer for measuring High-Temperature molten salts	10
High-temperature oxidation of Zr-4 and Zr-1Nb-O alloys: Influencing factors, oxidation behaviors and mechanisms	10
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
Experimental investigation on the effect of direct contact condensation regime on thermal stratification	9
The integration of seawater desalination system with nuclear power plant: Operational flexibility enhancement and thermo-economic performances	9
Structural optimization of gas-solid separator used in TMSR-SF based on computational fluid dynamics	9
Jet cross-flow induced vibrations in rod bundles. Part II: Transverse vibration results and excitation mechanisms	9
Performance analysis and optimization of heat pipe-based radiator for space nuclear power system	9
Resumption of water capsule reactivity-initiated accident testing at TREAT	9
Automatic recognition system for document digitization in nuclear power plants	9
Hunting for the correct pressure drop in a scaled reactor pool: Effect of geometry, mesh resolution, turbulence model and mass flow	9
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm	9
Safety margin quantification by integrating probabilistic and deterministic safety assessments — Application to design extension conditions	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
Time-series forecasting of a typical PWR system response under Control Element Assembly withdrawal at full power	9
Impact of measurement error on deep neural networks for nuclear material accountancy	9
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	9
Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX	9
Thermal hydraulic review of light water reactor based on subchannel code CTF	9
SI: Best of HTR 2021	9
Investigation of the fission gas release and grain boundary percolation in oxide fuels: A COMSOL multiphysics-based study	9
The possibility of utilizing novel cladding materials instead of zirconium in light water reactors	9
Spark plasma sintering of fuel meats for U3O8 based dispersion fuels	9
Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. II. Radioactive waste management	9
Interfacial area transport modeling of air–water bubbly two-phase flows in inclined orientations	9
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
Fuel depletion study of the molten salt demonstration reactor	9
Thermo-structural analysis of a dump nozzle for conducting hot liquid sodium	9
Outcomes and achievements from researches orienting the future in nuclear fission technology: NFT-18: Brazil, Peru and Bolivia	9
Difference in accumulation of plutonium and curium isotopes formed in americium targets irradiated in Joyo and JMTR	9
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	9
The cladding damage parameter under normal operating conditions in VVER fuel design: Resolving contradictions	9
Numerical study on the effects of tube inclination angle and heat conductive cover plate on freeze plug performance in molten salt reactors	9
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	9
DAVINCI-SP tests for debris bed formation and spreading in a pool with center conical structure under two-phase condition	9
Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundle	9
Investigation of dog-boning & fishtailing defects in plate type dispersion fuel Rolling: Insights from finite element analysis and defect minimization techniques	9
Editorial Board	9
Safety considerations related to boron redistribution during Loss-of-Coolant-Accident initiated beyond design basis events for the NuScale power module	9
Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way	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
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	9
Statistical analysis of the effect of lead-bismuth eutectic on fatigue resistance of 316L	9
Development of a droplet size model for the separated gas–liquid flow in horizontal pipe and its application	9
Study on the removal behavior of corrosion products by mixed-bed ion exchange column in PWR	9
Calculation of shutdown gamma distribution in the high temperature engineering test reactor	9
Fundamental and applied investigations of the liquid-metal cooled fast reactor thermal hydraulics (achieved results and further investigation issues)	9
Experimental and numerical investigation on dynamic characteristic of nozzle check valve and fluid-valve transient interaction	9
Temperature field of multi-barrier with gap layer in nuclear waste repository	9
Energy loss analysis in cavitation flow of a continuous-resistance trim	9
Data Adequacy by an Extended Analytic Hierarchy Process for Inverse Uncertainty Quantification in Nuclear Safety Analysis	9
Study on seismic safety evaluation of crossover pipeline connecting containment and turbine building in three-dimensional isolated nuclear power plant	9
Neutronics simulation of China Experimental Fast Reactor start-up tests using FARCOB and ERANOS 2.1 code systems	9
Modeling of axial flow-induced vibrations of a BWR instrumentation guide tube experiment	9
Modelling of a passive hydraulic lock concept for the mitigation transfer tubes in a SFR core	9
A shape function approach for predicting deteriorated heat transfer to supercritical pressure fluids on account of a thermal entry length phenomenon	9
Numerical analysis on flow distribution of nuclear reactor core inlet under ocean conditions	9
Study on gas–liquid two-phase flow in the suction chamber of a centrifugal pump and its dimensionless characteristics	8
Test program and numerical studies on reinforced concrete slabs impacted by liquid-filled missiles	8
RELAP5 validation for core makeup tank analysis based on separate effect tests	8
A closer-look on W and Pb alloys: In-depth evaluation in elastic modulus, gamma-ray, and neutron attenuation for critical applications	8
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	8
Heat transfer and flow characteristics of straight-type PCHEs with rectangular channels of different widths	8
Numerical investigation of oxidation and dissolution behavior in the fuel cladding using MPS-CV method	8
Assessing molten chloride salt components: Insights from a test loop experiment	8
Experimental study on boundary-conditioned hydration impact on bentonite gas permeability with supporting modeling	8
A fractional PID controller based on fractional point kinetic model and particle swarm optimization for power regulation of SMART reactor	8