Nuclear Engineering and Design

Article	Citations
Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation	55
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement	50
A review on the state of thermal hydraulics research on air ingress scenarios in High-Temperature Gas-cooled Reactors following a D-LOFC	46
Dynamic modeling and simulation of the GAMA-AHR	45
Rapid deep learning prediction model using satellite imagery for radiation accident Announcement system in Serbia	44
Thermo-fluid dynamic analysis of HLM pool. Circe experiments	42
National context of the recent Spanish research on nuclear fission technology	40
An educational simulation of a country’s electric power system	40
Analysis of NERVA engine performance using point kinetics-based power balance modeling	38
State feedback control of HPR1000 average coolant temperature based on dominant pole	38
Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes	38
A viscoplastic approach to corium spreading during a severe nuclear accident	37
Spanish contribution to the development and application of best estimate plus uncertainty methodologies: Past, present and future	37
The actual constraints and consequences of the maneuvering operation of PWRs — An optimum seeking approach	36
Corrigendum to “R&D in advanced technology fuels (ATFs) in Spain” [Nucl. Eng. Des 424, (2024) 113246]	32
Assessment of the disposability of radioactive waste inventories for a range of nuclear fuel cycles: Effect of repository size on disposal cost	32
Probability-based assessment of time-varying prestress losses in in-service containment structures	32
A numerical study on metallic melt infiltration in porous media and the effect of solidification	32
Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutions	31
Reliability Assessment of Safety-Critical Systems of Nuclear Power Plant using Ordinary Differential Equations and Reachability Graph	31
Real-time point-kinetics: Empirical laws, frontiers, and energy consistency	29
High-fidelity forced convection simulations of the University of Wisconsin–Madison air-cooled reactor cavity cooling system	28
Charging characteristics of typical alpha-emitting aerosols and their divergence from beta-emitters in nuclear emergency scenarios	28
Development and validation of theoretical-computational model for nuclear powered hydrogen production: A case study for Saudi Arabia	26
The impact of Rudi J. J. Stamm'ler on the development of the nuclear industry in Argentina	26

Integrated latent risk of radiological damage under conflict situation – Part II: Application and results	26
Dissolution experiments with surrogate treated organic wastes immobilized by hot isostatic pressing	26
Derivation and validation of a turbulent Prandtl number model for LBE in rod bundle channels	25
Conceptual design of GPT-marine reactor: Modernizing the ML-1 architecture with sCO2 direct cycle toward self-regulating marine propulsion	25
Study on heat transfer enhancement mechanism and performance evaluation of streamline spirally coiled tubes	25
Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors	24
Disruptive thermal-spectrum molten salt breeder reactor fuel cycle technologies	24
Selection of projects’ primary and secondary mitigation actions through optimization methods in nuclear decommissioning projects	24
Performance evaluation of nuclear fuel in a reactor based on the CAREM 25	24
Design of a foreign object retrieval robot for the internal lower head of a nuclear power plant pressurizer	23
Laser welding of PHWR end caps: A characterization study	23
Validation of RANS simulations on a 61-pin wire-wrapped fast-reactor fuel assembly under the presence of localized blockages	23
Effect of brazing parameter and Zr-Cu-Ti powder filler metal on the microstructure and mechanical properties of SiC ceramic joints	22
Development of plutonium fuel facility decommissioning technology to accelerate glovebox dismantling and reduce air-fed suits based operations	22
In-plane fluidelastic instability study of a tube bundle with a rotated triangular layout and small pitch ratio	22
Aircraft impact: Coupled dynamic simulations part 1: Modelling aspects	22
Comparative study of a glovebox dismantling facility for manual and remote glovebox dismantlement activities	22
Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project	21
Effect of rolling motions on the single and two-phase pressure drop in annulus channel with helical-finned heater for floating nuclear reactor	21
Progress of sodium-cooled fast reactor developments in Japan taking into account total lifecycle, risk-informed approach, and sustainability	21
Blast response of a scaled reinforced concrete structure with Two-Leaf cavity infill wall	21
SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability	21
Simulation and optimization of a conical type swirl-vane separator in nuclear SG	21
Robust a posteriori estimation of probit-lognormal seismic fragility curves via sequential design of experiments and constrained reference prior	21
Transient behavior of a molten salt fast reactor under two-phase flow conditions with helium bubbling	21
Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors	21
Analysis of heat pipe cooled reactor startup characteristics by multi-physics coupling simulation based on MOOSE framework	21
Bubble generation and migration behavior in SGTR accident of LFR from a series of experiments	20
Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle	20
Preface for special issue “NFT-06“: Nuclear fission technology in Slovenia, Croatia and Serbia	20
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics	20
Implications of using nanoparticles on the performance and safety of nuclear systems	20
Static-dynamic coupled analysis of pumping station structure of a nuclear power plant using viscoelastic static-dynamic unified artificial boundary	20
Influence of steam deviation, droplets mass flow rate and residual power on dispersed flow film boiling at sub-channel scale in LOCA conditions	20
Development and assessment of a reactor system prognosis model with physics-guided machine learning	20
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves	20
Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core	20
Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor	19
Design of electrical feedouts for hard-core components in nuclear power plants	19
Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model	19
Sub-channel analysis of the influence of the ATF cladding corrosion on thermal hydraulic behaviors	19
Burnup determination of Full-Scale, High-Density U3Si2-Al (4.8 gU/cc) fuel plate using destructive radiochemical technique	19
Feasibility of using BeO rods as secondary neutron sources in the long-life fuel cycle high-temperature gas-cooled reactor	19
Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow	19
Thermal-pressure coupled loading of large-scale nuclear containment model	18
Simulation of flow field characteristics around longitudinally staggered variable-curvature helical coil bundles	18
Research on gaseous and liquid source term of tritium for pressurized water reactor	18
A multi-level sensitivity analysis for the model parameters of the main steam system in nuclear power plants	18
Editorial Board	18
Editorial Board	18

Analysis of decay heat in spent nuclear fuel using serpent 2 simulations and Clab measurements	18
Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python	17
Application of a gamma spectrometric method for in situ determination of surface and volume activity of radioactive waste using a CeBr3 scintillation detector: Metallic waste case	17
Experimental study on the laser cutting process of the stainless steel hexagonal tube of fast reactor simulate assembly	17
Radial reflector macroscopic cross sections preparation impact on the low neutron leakage core Beavrs	17
Phosphoric acid-activated metakaolin-based geopolymer: Optimizing P/A molar ratio to solidify Cs+ and Sr2+ in nuclear waste	17
Study on flow-induced noise characteristics of multistage depressurization valve in the nuclear power plant	17
Robust multipole approach for continuous nuclear Data: RKFIT implementation for X2 VVER-1000 reactor benchmark	17
Development of core support barrel installation tool for a bypass flow reduction in nuclear reactor core	17
Porous Flow Modeling of Axial Gas Redistribution in Fragmented LWR Fuel Rods using MOOSE	16
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	16
Towards strategic agenda for European nuclear education, training, and knowledge management	16
Development of STEAM code: a steam generator tube-level three-dimensional thermal–hydraulic analysis platform	16
A novel approach for full-core mesh generation to enable high-fidelity thermal-hydraulic simulation of nuclear reactor engineering	16
Numerical analysis of developing laminar flows from a helical pipe to a straight pipe	16
A fouling prediction method for analyzing deposition distribution in double-side once through steam generator with helical tubes	16
Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite	16
Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo	16
Advancing inherent safety in small modular reactors: A CFD-based analysis of the PIUS concept	16
The application of the fixed-point iteration acceleration in the neutronics and thermal-hydraulics coupling calculation	16
Effects of swirl intensity on interfacial and wall friction factors of annular flows in a vertical pipe	16
A new pebble tracking method for 3D granular flow in pebble-bed reactor geometry	16
Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system	16
A data-driven reduced-order modeling approach for state estimation in IPWR forced-to-natural circulation transitions	15
Editorial Board	15
Developing reference-based correlations for temperature distribution in VVER reactor using gene expression programming and single-heated channel approach	15
CATHARE calculation of the tests conducted on the ELSMOR passive heat removal system	15
Analyses of the MELCOR capability to simulate integral PWR using passive systems in a DBA scenario	15
EDITORIAL NOTE AT THE SPECIAL ISSUE: NEA/CSNI/WGAMA specialists meeting on nuclear thermal-hydraulics in water cooled reactors	15
Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator	15
Improving operational flexibility of the integrated pressurized water reactor with the MED-TVC desalination system by control logic systems in the off-design mode	15
Validation of URANS and STRUCT-ε turbulence models for stratified sodium flow	15
Thermal limits calculation for a BWR plant Simulator	15
Comprehensive safety analysis and advanced design features of the SMART100 small modular reactor	15
Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly	15
Development of a coarse-mesh subchannel CFD model for prediction of core thermal–hydraulics in natural circulation conditions	15
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release	15
Transient fuel behavior analysis of UN fuel with a two-layered SiC cladding based on multiphysics method	15
Modeling of atmospheric dispersion and radiological dose consequences for a hypothetical accident in the perspective of Rooppur Nuclear Power Plant (RNPP)	15
An efficient method for input uncertainty propagation in CFD and the application to buoyancy-driven flows	15
Developing a fragility assessment procedure for fault displacement based on SSHAC level 2 process	15
Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactor	15
Demonstration of the inherent safety feature of HTGRs through the loss-of-forced-cooling test in the HTTR	15
Dynamics optimization of small branch pipes in nuclear power plants based on machine learning algorithms	15
Experimental investigation of subcooled flow boiling characteristics of water in vertical helically coiled tubes	14
Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs	14
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	14
A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning	14
Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident	14
Development of robustness assessment methodology for passive safety system against potential performance issue	14
Editorial Board	14
ANItA – A new Swedish national competence centre in new nuclear power technology	14
Optimization research of heat transfer coefficient prediction model for supercritical water based on Bayesian search algorithm	14
Dynamic dose equivalent rate estimation in dismantling: Physic-informed surrogate modeling	14
Verification of NODAL3 code with PWR MOX/UO2 core transient benchmark	14
Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark	14
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark	14
Experimental investigations into the rocking response of graphite-block assemblies in a HTGR core under horizontal earthquake shaking	14
Optimization of IEA-R1 reactor core parameters using the particle swarm algorithm	14
Ultra-real-time model reduction for nuclear reactor primary circuit calculation	14
U&S analyses in a BWR NPP LB-Loca transient with ATF	14
Review of CHF experiment and prediction methods under motion condition	14
Multi-physics simulation of a load rejection transient in a Pressurized water reactor. Comparison against experimental data, sensitivity and uncertainty study	14
Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments	14
Assessment of radiological consequences to a hypothetical accident of the 3-MW TRIGA Mark-II nuclear research reactor of Bangladesh	14
Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors	14
Conceptual design of small innovative helium-xenon cooled mobile nuclear power system	14
A surrogate-assisted evolutionary algorithm for robust scheduling of nuclear power plant construction under project risk interactions	14
Neutron single-flow method for efficient production of Cf-252 in high-flux fast reactor	14
Establishing control points scheme and baseline measurements for environmental radioactivity monitoring: A case study of the nuclear Institute	14
Multiphysics modeling approach for the analysis of noble metals deposition in the Molten Salt Fast Reactor	14
Flow-induced vibration of core barrel of small modular reactor: Fluctuating pressure	14
Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactor	14
Structural optimization of gas-solid separator used in TMSR-SF based on computational fluid dynamics	13
Study on the thermal hydraulic performance of a separated structure shell-and-tube steam generator under various operating conditions	13
Investigation of the fission gas release and grain boundary percolation in oxide fuels: A COMSOL multiphysics-based study	13
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	13
Automatic recognition system for document digitization in nuclear power plants	13
Study on the integrity of prolonged steam oxidized clad column quenched at various reflood rates	13
Pre − test evaluation of a grid − spaced deformed fuel pin bundle	13

New correlations for focusing effect evaluation of the light metal layer in the lower head of a nuclear reactor in case of severe accident	13
Spark plasma sintering of fuel meats for U3O8 based dispersion fuels	13
Dynamic study of a steam Rankine cycle using CATHARE-3 system thermal-hydraulic code: Application to Superphenix fast reactor	13
Mapping of the potential involvement of national companies to fulfilment of local content requirements in HTGR construction projects in Indonesia	13
Numerical appraisal of the role of heat transfer regimes on transient response of carbon dioxide based supercritical natural circulation loop during power upsurge	13
Novel methodology for functional design chain analysis of a nuclear power plant: A new built Finnish power plant case study	13
Research on predicting the diffusion of radionuclide in complex building scenarios based on a hybrid deep learning model	13
Performance analysis and optimization of heat pipe-based radiator for space nuclear power system	13
Numerical simulation of operational transients in sodium-cooled fast reactors	13
Study on the feasibility of dynamic rod worth measurement using fission chamber detector signal in HPR1000	13
Simulation of mixed convection heat transfer to liquid metals in vertical channels and pipes	13
Numerical transfer towards unresolved morphology representation in the MultiMorph model	13
Flow instabilities in helical-coil steam generators for small modular reactors: A review	13
Study of neutron flux redistribution and shadowing effect in rod worth measurements with the rod drop experiment	13
Study on seismic safety evaluation of crossover pipeline connecting containment and turbine building in three-dimensional isolated nuclear power plant	13
Scaling challenges in small modular reactor	13
Validation of modeling scheme implementing MULTID component of MARS-KS code to predict shell-side pressure drop in shell-and-tube type heat exchangers	13
Study on influence of asymmetric safety injection on reactor pressure vessel integrity evaluation	13
Calculation of shutdown gamma distribution in the high temperature engineering test reactor	13
Evaluation of fully developed turbulent friction coefficient in polygonal section ducts and ducts with corner angle 0° by new characteristic lengths	13
Reactor core design with enriched gadolinia burnable absorbers for soluble Boron-Free operation in the innovative SMR	13
Risk reduction by means of FLEX strategies in pressurized water reactors	13
A comparative study of oxide scales formed on Alloy 690 in deaerated supercritical water and supercritical CO2 at 600 °C	12
Research on control strategies for rapid load decrease events in fluoride salt reactor-supercritical CO2 Brayton cycle systems	12
Kernel principle component analysis and random under sampling boost based fault diagnosis method and its application to a pressurized water reactor	12
TRISO fuel performance analysis: Uncertainty quantification toward optimization	12
Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way	12
Research on simplification of branches method of accident sequences based on expert knowledge and heuristic optimization algorithm	12
Irregular pentagon loop for nuclear reactor natural circulation system test apparatus	12
Energy loss analysis in cavitation flow of a continuous-resistance trim	12
Spanish research related to SMRs projects	12
Developing a digital twin framework for remotely monitoring nuclear reactor facilities	12
Incorporation of uranium nitride fuel capability into the ENIGMA fuel performance code: Model development and validation	12
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	12
Thermal-hydraulic analysis of the superheated steam supply system in NHR200-II using refined semi-2D modeling	12
Experimental and numerical study of the influence of vent burst pressure on venting characteristic of hydrogen-air explosion	12
New multi-fluid model of pool scrubbing in bubble rise region	12
Fuel depletion study of the molten salt demonstration reactor	12
Effects of liquid viscosity on interfacial and wall friction factors of swirling annular flows in a vertical pipe	12
Corrigendum to “A study of ammonia-hydrogen-electricity cogeneration coupled to a very high-temperature heat source” [Nucl. Eng. Design 414 (2023) 112585]>	12
Assessing turbulence models in PWR sub-channel geometry using q-DNS	12
Assessment of radiation dose and environmental impact from design basis accidents at the BAEC TRIGA research reactor	12
An automated unsupervised anomaly detection framework for DCS controller logs in nuclear power plants	12
Modeling of axial flow-induced vibrations of a BWR instrumentation guide tube experiment	12
Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system	12
Radiation damage simulation of reactor pressure vessel material: A multi-scale approach	12
Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detection	12
Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport	12
Similarity studies of buoyancy effects in impinging jets – Application to SFR core	12
Novel dual-cooled assembly design and thermal hydraulic analysis for a 150 MWt small modular molten salt reactor core	12
Random vibration analysis of nuclear power plant structures	12
Parametric study of the influence of 135Xe build-up on required excess reactivity for load-following operations	12
Critical heat flux detection and temperature profile measurement with OFDR in a carbon dioxide cooled tube at high subcritical pressures	12
Integrated latent risk of radiological damage under conflict situation-part I: Concept and approach	12
Molten salt reactor system dynamics in simulink and modelica, a code to code comparison	12
Sensitivity analysis of main neutronic parameters of standard PWR and WWER-1000 pin cells to resonance self-shielding treatment methods and cross section libraries	12
Construction schedule and cost risk for large and small light water reactors	12
Investigation on the Irradiation-thermal–mechanical coupling behaviors of the solid Microencapsulated fuel rod	12
Fundamental and applied investigations of the liquid-metal cooled fast reactor thermal hydraulics (achieved results and further investigation issues)	11
A novel method of estimating earthquake durations for the analysis of floor vibrations of nuclear power plants	11
High-temperature oxidation of Zr-4 and Zr-1Nb-O alloys: Influencing factors, oxidation behaviors and mechanisms	11
Improved and extended correlation for critical heat flux in annuli	11
Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundle	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
Interfacial area transport modeling of air–water bubbly two-phase flows in inclined orientations	11
Reverse application of the Andrews protocol for assessing risks in a hypothetical nuclear accident	11
Numerical investigation about radius ratio effect of helical tubes in the heat exchanger	11
Statistical analysis of the effect of lead-bismuth eutectic on fatigue resistance of 316L	11
Mechanistic prediction of Westinghouse TRITON11® BWR fuel critical power with MEFISTO-T subchannel analysis code	11
Subgroup method for the high fidelity neutronics code SHARK and preliminary benchmarking	11
Application of data assimilation in searching better lattice-physics parameters of fuel assembly	11
Outcomes and achievements from researches orienting the future in nuclear fission technology: NFT-18: Brazil, Peru and Bolivia	11
Generic material irradiation database for delayed heating calculations	11
Time-series forecasting of a typical PWR system response under Control Element Assembly withdrawal at full power	11
Assuring fire safety in nuclear plants with international standards	11
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment	11
Modelling of a passive hydraulic lock concept for the mitigation transfer tubes in a SFR core	11
Data Adequacy by an Extended Analytic Hierarchy Process for Inverse Uncertainty Quantification in Nuclear Safety Analysis	11
Delay impact mechanism of Spent Fuel Cask without assuming content dropping inside packaging	11
Experimental investigation on hot water rapid depressurization process characteristics inside and outside of the ruptured pipeline	11
A modified mental workload model based on CREAM in the complex scenarios of advanced main control room in the nuclear power plant	11
A novel experimental observation of the gravity-driven flashing of metastable water in a heated pool	11
Impact of measurement error on deep neural networks for nuclear material accountancy	11
MAGIC-GPS global variance reduction method for large-scale shielding calculation	11
Editorial Board	11
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]	11
Comprehensive considerations for the co-decontamination and recycling of radioactively contaminated steels	11
High-Throughput falling ball viscometer for measuring High-Temperature molten salts	11
N-Euler mathematical modelling and numerical simulation of liquid–gas–solid flows	11
Experimental investigation on the effect of direct contact condensation regime on thermal stratification	11
SI: Best of HTR 2021	11
RELAP5 validation for core makeup tank analysis based on separate effect tests	11
Design of fuel-failure monitoring system for water-cooled reactor	11
Iterative computed tomography reconstruction of void fraction in a fuel bundle on unstructured mesh	11
Helium-air mixing in simulated reactor cavities of high temperature gas reactors	11