Nuclear Engineering and Design

Article	Citations
Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration	60
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	56
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	46
A numerical study on metallic melt infiltration in porous media and the effect of solidification	41
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	39
Performance evaluation of AHWR flux mapping system during normal operational scenarios	39
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	39
Measurement of corium surface tension using the maximum bubble pressure	38
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	34
Assessment of TRU burning in a molten salt reactor moderated by zirconium hydride rods	33
Editorial Board	32
Study on improvement for the prediction accuracy of natural circulation flow rate by investigating void fraction correlation	31
The fluid-structure interaction effect on seismic response of double CAP1400 spent fuel storage racks	29
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	29
Modeling of Am-241 as an alternative fuel source in a radioisotope thermoelectric generator	28
“Ion sputtering – thermal separation” technology for spent nuclear fuel processing	28
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels	27
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	27
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	26
An educational simulation of a country’s electric power system	26
National context of the recent Spanish research on nuclear fission technology	25
Depressurization of nuclear power plants through a silica gel-based system	24
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	24
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	23
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	23

Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	22
Design of specimen holders for flow accelerated corrosion experiments in molten lead with numerical evaluation of pressure losses	22
A viscoplastic approach to corium spreading during a severe nuclear accident	22
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	22
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	22
Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL	22
Aircraft impact: Coupled dynamic simulations part 1: Modelling aspects	22
Quantification of uncertainties due to manufacturing tolerances using deterministic sampling methods	22
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment	21
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	21
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	21
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I	20
Literature survey of droplet entrainment from water pools	20
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics	20
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	20
Assessment of wall heat flux partitioning model for two-phase CFD	20
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	20
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves	19
Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core	19
Effect of inclination angle of lower tube on saturated pool boiling heat transfer of upper tube	19
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	19
Development and assessment of a reactor system prognosis model with physics-guided machine learning	19
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	19
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	18
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	18
Implications of using nanoparticles on the performance and safety of nuclear systems	18
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	18
State feedback control of HPR1000 average coolant temperature based on dominant pole	18
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	17
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	17
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	17
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	17
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	17
Coupled porous media approaches in sub-channel CFD	16
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	16
Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow	16
EDITORIAL NOTE AT THE SPECIAL ISSUE: NEA/CSNI/WGAMA specialists meeting on nuclear thermal-hydraulics in water cooled reactors	16
Experimental study of air–steam condensation on the influence of tube diameter and inclination angle	16
Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER	16
Implications of HALEU fuel on the design of SMRs and micro-reactors	16
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	16
Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe	16
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	16
Review of research using analogy concept for thermal hydraulic and severe accident experiments	16
Editorial Board	15
Editorial Board	15
Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python	15
Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo	15
Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator	15
Editorial Board	15

Editorial Board	15
Investigation on the hydraulic process of inertia tank in the case of pump trips	15
Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow	15
Numerical transfer towards unresolved morphology representation in the MultiMorph model	15
Online identification of trips caused by the external proton source in an ADS reactor	15
Editorial Board	15
Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident	15
Establishing control points scheme and baseline measurements for environmental radioactivity monitoring: A case study of the nuclear Institute	15
Risk reduction by means of FLEX strategies in pressurized water reactors	15
Development of core support barrel installation tool for a bypass flow reduction in nuclear reactor core	15
Effects of swirl intensity on interfacial and wall friction factors of annular flows in a vertical pipe	15
ANItA – A new Swedish national competence centre in new nuclear power technology	14
Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite	14
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark	14
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	14
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	14
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors	14
A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning	14
Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactor	14
Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system	14
Radial reflector macroscopic cross sections preparation impact on the low neutron leakage core Beavrs	14
Development of a coarse-mesh subchannel CFD model for prediction of core thermal–hydraulics in natural circulation conditions	14
Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs	13
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	13
Monitoring of helium gas leakage from canister storing spent nuclear fuel: Radiological consequences and management	13
Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark	13
Flow instabilities in helical-coil steam generators for small modular reactors: A review	13
Phosphoric acid-activated metakaolin-based geopolymer: Optimizing P/A molar ratio to solidify Cs+ and Sr2+ in nuclear waste	13
Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR	13
Review of CHF experiment and prediction methods under motion condition	13
Validation of URANS and STRUCT-ε turbulence models for stratified sodium flow	13
Experimental investigation of subcooled flow boiling characteristics of water in vertical helically coiled tubes	13
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release	13
Experimental study on the laser cutting process of the stainless steel hexagonal tube of fast reactor simulate assembly	13
Eigenvalue sensitivity and nuclear data uncertainty analysis for the Moroccan TRIGA Mark II research reactor using SCALE6.2 and MCNP6.2	13
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics method	13
Towards strategic agenda for European nuclear education, training, and knowledge management	13
Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly	13
Dynamic dose equivalent rate estimation in dismantling: Physic-informed surrogate modeling	13
Numerical analysis of developing laminar flows from a helical pipe to a straight pipe	12
A scoping study on debris bed formation from metallic melt coolant interactions	12
Developing reference-based correlations for temperature distribution in VVER reactor using gene expression programming and single-heated channel approach	12
Dynamics optimization of small branch pipes in nuclear power plants based on machine learning algorithms	12
An efficient method for input uncertainty propagation in CFD and the application to buoyancy-driven flows	12
Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark	12
Investigation into different 1D/3D co-simulation methodologies applied to a natural circulation loop	12
Neutron single-flow method for efficient production of Cf-252 in high-flux fast reactor	12
Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments	12
A novel approach for full-core mesh generation to enable high-fidelity thermal-hydraulic simulation of nuclear reactor engineering	12
Simulation of mixed convection heat transfer to liquid metals in vertical channels and pipes	12
Experience of mixed nitride uranium–plutonium fuel fabrication at the siberian chemical plant jsc site	12
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithm	12
Thermal limits calculation for a BWR plant Simulator	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
Flow-induced vibration of core barrel of small modular reactor: Fluctuating pressure	12
Numerical investigation of vapor bubble condensation in subcooled quiescent water	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
Experimental and numerical study of 19-pin disassembled fuel channel under severe accident condition	12
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark	12
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	12
Research on gaseous and liquid source term of tritium for pressurized water reactor	12
Study on flow-induced noise characteristics of multistage depressurization valve in the nuclear power plant	12
Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh	11
Experimental and numerical investigation on dynamic characteristic of nozzle check valve and fluid-valve transient interaction	11
Simulation of natural circulation cartridge loop experiments and application to molten salt reactors	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
Natural convection phenomena in a liquid metal pool due to relocated and heap of heat-generating core debris: Numerical study	11
Assuring fire safety in nuclear plants with international standards	11
Comprehensive considerations for the co-decontamination and recycling of radioactively contaminated steels	11
New multi-fluid model of pool scrubbing in bubble rise region	11
Sub-channel analysis of the influence of the ATF cladding corrosion on thermal hydraulic behaviors	11
Modeling of atmospheric dispersion and radiological dose consequences for a hypothetical accident in the perspective of Rooppur Nuclear Power Plant (RNPP)	11
Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod	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
Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates	11
Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia	11
An assessment of radiation exposure of workers during decommissioning of reactor vessel at Kori #1 unit	11
Study on seismic safety evaluation of crossover pipeline connecting containment and turbine building in three-dimensional isolated nuclear power plant	11

Validation of numerical models for seismic fluid-structure-interaction analysis of nuclear, safety-related equipment	11
Corrigendum to “Integral LOCA fragmentation test on high-burnup fuel” [Nucl. Eng. Design (2020) 367 110811, ISN 0029-5493]	11
Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system	11
Incorporation of uranium nitride fuel capability into the ENIGMA fuel performance code: Model development and validation	11
Validation of modeling scheme implementing MULTID component of MARS-KS code to predict shell-side pressure drop in shell-and-tube type heat exchangers	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
Parametric study of the influence of 135Xe build-up on required excess reactivity for load-following operations	11
High-Throughput falling ball viscometer for measuring High-Temperature molten salts	11
Long term cooling safe shutdown performance analysis for SMART with passive safety system using MARS-KS	11
Evaluation of fully developed turbulent friction coefficient in polygonal section ducts and ducts with corner angle 0° by new characteristic lengths	11
Interfacial area transport modeling of air–water bubbly two-phase flows in inclined orientations	10
Fuel depletion study of the molten salt demonstration reactor	10
Study on influence of asymmetric safety injection on reactor pressure vessel integrity evaluation	10
Development of singular value decomposition based solution scheme for a numerical simulation of multiphase flow	10
Energy loss analysis in cavitation flow of a continuous-resistance trim	10
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment	10
Scaling challenges in small modular reactor	10
Similarity studies of buoyancy effects in impinging jets – Application to SFR core	10
Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detection	10
Irregular pentagon loop for nuclear reactor natural circulation system test apparatus	10
Investigation of the fission gas release and grain boundary percolation in oxide fuels: A COMSOL multiphysics-based study	10
Calculation of shutdown gamma distribution in the high temperature engineering test reactor	10
Structural optimization of gas-solid separator used in TMSR-SF based on computational fluid dynamics	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
Dynamic study of a steam Rankine cycle using CATHARE-3 system thermal-hydraulic code: Application to Superphenix fast reactor	10
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm	10
Assessing turbulence models in PWR sub-channel geometry using q-DNS	10
Modeling of axial flow-induced vibrations of a BWR instrumentation guide tube experiment	10
Construction schedule and cost risk for large and small light water reactors	10
Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundle	10
Development of a droplet size model for the separated gas–liquid flow in horizontal pipe and its application	10
Spark plasma sintering of fuel meats for U3O8 based dispersion fuels	10
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	10
Analysis on helium stratification erosion by vertical steam jet using the CUPID code	10
TRISO fuel performance analysis: Uncertainty quantification toward optimization	10
Experimental investigation on the effect of direct contact condensation regime on thermal stratification	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
Time-series forecasting of a typical PWR system response under Control Element Assembly withdrawal at full power	10
Novel methodology for functional design chain analysis of a nuclear power plant: A new built Finnish power plant case study	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
Effects of liquid viscosity on interfacial and wall friction factors of swirling annular flows in a vertical pipe	9
Temperature field of multi-barrier with gap layer in nuclear waste repository	9
Outcomes and achievements from researches orienting the future in nuclear fission technology: NFT-18: Brazil, Peru and Bolivia	9
A modelling methodology for the description of helium behaviour accounting for the grain-size distribution	9
Kernel principle component analysis and random under sampling boost based fault diagnosis method and its application to a pressurized water reactor	9
Experimental study on fuel depressurization and its effect on dispersion	9
A shape function approach for predicting deteriorated heat transfer to supercritical pressure fluids on account of a thermal entry length phenomenon	9
Subgroup method for the high fidelity neutronics code SHARK and preliminary benchmarking	9
Thermo-structural analysis of a dump nozzle for conducting hot liquid sodium	9
Site response analysis: Uncertain motions propagating through uncertain elastoplastic soil	9
Study on the removal behavior of corrosion products by mixed-bed ion exchange column in PWR	9
Generic material irradiation database for delayed heating calculations	9
CFD simulation plus uncertainty quantification of the mixing of two fluid with different density for the Cold-Leg mixing benchmark	9
Iterative computed tomography reconstruction of void fraction in a fuel bundle on unstructured mesh	9
Automatic recognition system for document digitization in nuclear power plants	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
Coupled neutronics and thermal-hydraulics transient simulation of a gas-cooled reactor in the aircraft nuclear propulsion system	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 study on thermally assisted sagging deflection and interaction of multiple coolant channels	9
Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-1: Spreading models, numerical solution methods and verifications	9
The integration of seawater desalination system with nuclear power plant: Operational flexibility enhancement and thermo-economic performances	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
Thermal hydraulic review of light water reactor based on subchannel code CTF	9
Highly-detailed neutronic and thermal-hydraulic coupled calculations for OPAL reactor using diverse codes and approaches	9
Design of a portable backup shutdown system for the high temperature gas cooled reactor	9
Estimating degradation growth rate and time of component replacement from limited inspection data using mixed-effects modelling	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
Elements of importance for research in nuclear safety for upcoming decades – A personal perspective	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
The possibility of utilizing novel cladding materials instead of zirconium in light water reactors	9
Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way	9
SI: Best of HTR 2021	9
Numerical simulation of operational transients in sodium-cooled fast reactors	9
Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX	9
Performance analysis and optimization of heat pipe-based radiator for space nuclear power system	9
Mechanistic prediction of Westinghouse TRITON11® BWR fuel critical power with MEFISTO-T subchannel analysis code	9
Molten salt reactor system dynamics in simulink and modelica, a code to code comparison	9
Fundamental and applied investigations of the liquid-metal cooled fast reactor thermal hydraulics (achieved results and further investigation issues)	9
Difference in accumulation of plutonium and curium isotopes formed in americium targets irradiated in Joyo and JMTR	9
Mixed convection around two vertically aligned horizontal cylinders: A numerical, experimental, and modeling investigation on the effect of local conditions on heat transfer	9
Editorial Board	9
Thermodynamic equilibrium state calculations for oxidation and corrosion reactions of B4C and oxide-based neutron absorber compounds in reactor control rods	9
Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. II. Radioactive waste management	9
Experimental study on combined reflooding phenomenon and RELAP5 simulation analysis in narrow rectangular channel	9
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	9
A new correlation for post-dryout heat transfer in upward vertical flow	9
Spanish research related to SMRs projects	9
Numerical investigation on steam condensation and heat transfer in an emergency condenser tube with the thermo-hydraulic system code ATHLET	9
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	9
Investigation of dog-boning & fishtailing defects in plate type dispersion fuel Rolling: Insights from finite element analysis and defect minimization techniques	9
Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application	9
Neutronics simulation of China Experimental Fast Reactor start-up tests using FARCOB and ERANOS 2.1 code systems	9
The LIFUS5 separate effect test facility experimental programme	8
Heat transfer and flow characteristics of straight-type PCHEs with rectangular channels of different widths	8
Measurement of ablation and estimation of the interfacial heat flux profiles during molten corium concrete interactions	8