Progress in Nuclear Energy

Papers
(The median citation count of Progress in Nuclear Energy is 2. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-11-01 to 2024-11-01.)
ArticleCitations
Do renewable and nuclear energy enhance environmental quality in France? A new EKC approach with the load capacity factor235
Do nuclear energy and renewable energy surge environmental quality in the United States? New insights from novel bootstrap Fourier Granger causality in quantiles approach149
Nuclear energy: A pathway towards mitigation of global warming128
Revealing the nexus between nuclear energy and ecological footprint in STIRPAT model of advanced economies: Fresh evidence from novel CS-ARDL model120
BaO–Li2O–B2O3 glass systems: Potential utilization in gamma radiation protection106
Dense and environment friendly bismuth barium telluroborate glasses for nuclear protection applications83
Synthesis, physical and nuclear shielding properties of novel Pb–Al alloys82
Review of nuclear microreactors: Status, potentialities and challenges75
Do globalization and nuclear energy intensify the environmental costs in top nuclear energy-consuming countries?70
Identifying the strategic priorities of nuclear energy investments using hesitant 2-tuple interval-valued Pythagorean fuzzy DEMATEL67
Numerical study on the thermal performance of the shell and tube heat exchanger using twisted tubes and Al2O3 nanoparticles66
Effect of Fe2O3 doping on structural, FTIR and radiation shielding characteristics of aluminium-lead-borate glasses65
Study of comprehensive shielding behaviors of chambersite deposit for neutron and gamma ray64
Comparative shielding features for X/Gamma-rays, fast and thermal neutrons of some gadolinium silicoborate glasses63
Nuclear shielding properties and buildup factors of Cr-based ferroalloys61
Radiation shielding properties of concrete containing magnetite60
Solidification of radioactive wastes by cement-based materials55
A review of VOF methods for simulating bubble dynamics51
Shielding performance of heavy-weight ultra-high-performance concrete against nuclear radiation50
Economics and finance of Molten Salt Reactors46
Consistency and shielding efficiency of cement-bitumen composite for use as gamma-radiation shielding material45
Core power control of a space nuclear reactor based on a nonlinear model and fuzzy-PID controller44
Low cost radiation shielding material for low energy radiation applications: Epoxy/Yahyali Stone composites43
Gamma-ray attenuation behaviors of hematite doped polymer composites43
MHD effects on natural convection in a U-shaped enclosure filled with nanofluid-saturated porous media with two baffles43
Experimental and FLUKA evaluation on structure and optical properties and γ-radiation shielding capacity of bismuth borophosphate glasses43
Transport, constructability, and economic advantages of SMR modularization41
Development of new heavy concretes containing chrome-ore for nuclear radiation shielding applications41
Enhancing the gamma-ray attenuation parameters of mixed bismuth/barium borosilicate glasses: Using an experimental method, Geant4 code and XCOM software40
Study of mixed convection in two layers of saturated porous medium and nanofluid with rotating circular cylinder39
A survey of multi-objective optimization methods and their applications for nuclear scientists and engineers38
Comparison of the error-integral performance indexes in a GA-tuned PID controlling system of a PWR-type nuclear reactor point-kinetics model38
Calculation of the gamma radiation shielding efficiency of cement-bitumen portable container using MCNPX code34
Synthesis of sodium alginate (SA)/ polyvinyl alcohol (PVA)/ polyethylene oxide (PEO)/ ZSM-5 zeolite hybrid nanostructure adsorbent by casting method for uranium (VI) adsorption from aqueous solutions34
Waste-polymer incorporated concrete mixes for neutron and gamma radiation shielding32
Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation32
Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2×2 helical cruciform rods31
The role of nuclear energy in the carbon neutrality goal31
Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM31
Numerical investigation of the flow and heat transfer of Al2O3/water nanofluid in a tube equipped with stationary and self-rotating twisted tapes30
Fabrication of novel neutron shielding materials: Polypropylene composites containing colemanite, tincal and ulexite30
Unsupervised machine learning techniques for fault detection and diagnosis in nuclear power plants29
Nuclear radiation shielding characteristics and physical, optical, mechanical, and thermal properties of lithium-borotellurite glass doped with Rb2O28
Recent progress in CdZnTe based room temperature detectors for nuclear radiation monitoring28
Arc welding of zirconium and its alloys: A review26
High-temperature corrosion of Zr–Nb alloy for nuclear structural materials26
Design of optimal fractional order fuzzy PID controller based on cuckoo search algorithm for core power control in molten salt reactors26
Development of deep reinforcement learning-based fault diagnosis method for rotating machinery in nuclear power plants26
Performance of heavy weight concrete incorporating recycled rice straw ash as radiation shielding material26
Fuzzy TOPSIS-based risk assessment model for effective nuclear decommissioning risk management26
Deep learning for safety assessment of nuclear power reactors: Reliability, explainability, and research opportunities26
Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neut25
Numerical investigation of heat-transfer enhancement in helically coiled spiral grooved tube heat exchanger25
Gamma radiation shielding performance of CuxAg(1-x)-alloys: Experimental, theoretical and simulation results25
Computational assessment of thermo-hydraulic performance of Al224
Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor24
Control automation in the heat-up mode of a nuclear power plant using reinforcement learning23
Performance study of ion exchange resins solidification using metakaolin-based geopolymer binder23
Optical and gamma-ray shielding effectiveness of a newly fabricated P2O5–CaO–Na2O–K2O–PbO glass system23
Investigation on shielding properties of lead based alloys23
Comparative study of the supercritical carbon-dioxide recompression Brayton cycle with different control strategies22
Gamma attenuation characteristics of CdTe-Doped polyester composites22
In-situ TEM observation of the evolution of dislocation loops and helium bubbles in a pre helium irradiated FeCrAl alloy during annealing22
Radiation shielding properties of selected alloys using EPICS2017 data library22
Evaluation of CdS doped polyester composites regarding gamma and neutron shielding properties22
Synthesis and characterization of Barium ferrite nano-particles for X-ray/gamma radiation shielding and display applications22
Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels21
The multi-objective inspection path-planning in radioactive environment based on an improved ant colony optimization algorithm21
Electro-adsorption characteristics and mechanism of Sr2+ ions by capacitive deionization and CFD analysis study21
Off-site modular construction and design in nuclear power: A systematic literature review20
A new neutronics-thermal-mechanics multi-physics coupling method for heat pipe cooled reactor based on RMC and OpenFOAM20
High impact tungsten-doped borosilicate glass composite for gamma and neutron transparent radiation shielding20
A binary composite material of nano polyaniline intercalated with Nano-Fe2O3 for enhancing gamma-radiation-shielding properties: Experimental and simulation study20
Radiation shielding performances of Na2SiO3 based low-cost micro and nano composites for diagnostic imaging20
Single-phase flow in helical cruciform fuel assembly with conjugate heat transfer20
Problems and perspectives of borehole disposal of radioactive waste20
Existing and potential decontamination methods for radioactively contaminated metals-A Review20
Bi2S3-reduced graphene oxide composite for gaseous radioiodine capture and its immobilization within glass composite material19
The dynamic links between nuclear energy and sustainable economic growth. Do institutions matter?19
Optimization of flexible square cascade for high separation of stable isotopes using enhanced PSO algorithm19
Fault diagnosis based on gated recurrent unit network with attention mechanism and transfer learning under few samples in nuclear power plants19
Abnormal event detection, identification and isolation in nuclear power plants using LSTM networks19
Borotellurite glass system doped with ZrO2, potential use for radiation shielding19
Gradient descent-particle swarm optimization based deep neural network predictive control of pressurized water reactor power19
3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM18
Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches18
The renewable and nuclear energy-economic growth nexus in the context of quality of governance18
Gamma and neutrons shielding using innovative fiber reinforced concrete18
Design and application of supervisory control based on neural network PID controllers for pressurizer system18
Radiation shielding properties of modified concrete mixes and their suitability in dry storage cask18
Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison18
Gels, coatings and foams for radioactive surface decontamination: State of the art and challenges for the nuclear industry17
Design, optimization and thermodynamic analysis of SCO2 Brayton cycle system for FHR17
Investigating the effects of natural gas, nuclear energy, and democracy on environmental footprint and energy risk in France: Does financial inclusion matter?17
Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR)17
Fundamental properties and radioactivity shielding performance of concrete recycled cathode ray tube waste glasses and electric arc furnace slag as aggregates17
Temperature effect on the thermal and hydraulic conductivity of Korean bentonite buffer material17
Application of model free active disturbance rejection controller in nuclear reactor power control17
Identification of two-phase flow regime in the energy industry based on modified convolutional neural network16
Application of polyaniline nanocomposites in the trapping of thorium ions from aqueous solutions:Adsorption equilibrium, kinetics and thermodynamics16
The important role and performance of engineered barriers in a UK geological disposal facility for higher activity radioactive waste16
Regress in nuclear district heating. The need for rethinking cogeneration16
Understanding the innovative developments with two-stage technology S-curve of nuclear energy projects16
Numerical investigation of gas-liquid two-phase flow in horizontal pipe with orifice plate16
Conceptual design and thermal-hydraulic analysis of a megawatt-level lead-bismuth cooling reactor for deep-sea exploration16
Investigations on Radiation Shielding properties of Leadaluminoborate nanocomposite16
Radiation shielding, photoluminescence and antimicrobial properties of Magnesium ferrite synthesized 16
Evaluation of Bentonite, attapulgite, and kaolinite as eco-friendly adsorbents in the treatment of real radioactive wastewater containing Cs-13716
Na2Si3O7/Ag micro and nano-structured glassy composites: The experimental and MCNP simulation surveys of their radiation shielding performances16
On the use of green concrete composite as a nuclear radiation shielding material15
Drift-flux model for upward dispersed two-phase flows in vertical medium-to-large round tubes15
Investigation of gamma-rays and fast neutrons attenuation parameters for NixCo1-xFe2O4 nickel ferrites15
PWR core pattern optimization using grey wolf algorithm based on artificial neural network15
CFD validation with optimized mesh using benchmarking data of pebble-bed high-temperature reactor15
Design of passive residual heat removal systems and application of two-phase thermosyphons: A review15
Robust-optimal integrated control design technique for a pressurized water-type nuclear power plant15
Finding a suitable fuel type for the disposal of the accumulated minor actinides in the spent nuclear fuel in PWR15
Wall boiling of Al2O3-water nanofluid: Effect of nanoparticle concentration15
Prospects for additive manufacturing of nuclear fuel forms15
History and status of spent fuel treatment at the INL Fuel Conditioning Facility15
Mass optimization of the radiation shadow shield for space nuclear power system14
137Cs ocean distribution and fate at East Mediterranean Sea in case of a nuclear accident in Akkuyu Nuclear Power Plant14
Radioactive decontamination of metal surfaces using peelable films made from chitosan gels and chitosan/magnetite nanoparticle composites14
Development of a plug-and-play anti-noise module for fault diagnosis of rotating machines in nuclear power plants14
A preliminary investigation on gamma-rayattenuation of alkali-activated concrete waste based-geopolymer modified with pozzocrete-fly ash14
Impact of alkali activated mortar incorporating different heavy metals on immobilization proficiency using gamma rays attenuation14
Optimization of the electricity generation mix using economic criteria with zero-emissions for stand-alone systems: Case applied to Grand Canary Island in Spain14
Cyber security in the nuclear industry: A closer look at digital control systems, networks and human factors14
Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety14
Applying analytic hierarchy process to industrial process design in a Nuclear Renewable Hybrid Energy System14
The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks: An experimental study14
Adaptive backstepping controller with extended state observer for load following of nuclear power plant13
Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment13
Kalman filter, particle filter, and extended state observer for linear state estimation under perturbation (or noise) of MHTGR13
Computational burnup analysis of the TRIGA Mark II research reactor fuel13
Sites selection for a potential radioactive waste repository in Peninsular Malaysia: GIS-based weight linear combination and multi-criteria decision-making analysis13
High-fidelity neutronics and thermal-hydraulics analysis of helical cruciform fuel based on small modular FHR13
Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM13
Experimental study of heat transfer characteristics on condensation in the presence of NCG through thermal resistance analysis13
Fenton oxidative degradation of spent organic solvents from nuclear fuel reprocessing plant13
Radiation shielding properties of flexible liquid metal-GaIn alloy13
Experimental investigation of aluminum fins on relative thermal performance of sintered copper wicked and grooved heat pipes13
Severe accident in high-power light water reactors: Mitigating strategies, assessment methods and research opportunities13
Asymmetric response of energy efficiency to research and development spending in renewables and nuclear energy usage in the United States13
Investigation of soil-water characteristic curves for compacted bentonite considering dry density13
Characterization of carbon fiber and glass fiber reinforced polycarbonate composites and their behavior under gamma irradiation12
GeN-ROM—An OpenFOAM®-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors12
The optimization of U(VI) removal by a novel amidoximated modified calcium alginate gel bead with entrapped functionalized SiO2 nanoparticles12
Tritium generation, release, and retention from in-core fluoride salt irradiations12
An analytical link of disaggregated green energy sources in achieving carbon neutrality in China: A policy based novel wavelet local multiple correlation analysis12
Explicit modeling of pebble temperature in the porous-media model for pebble-bed reactors12
Exergy optimization of nuclear-solar dual proposed power plant based on GWO algorithm12
Potential uses of different sustainable concrete mixtures in gamma and neutrons shielding purposes12
Investigation of a nanofluid-based natural circulation loop12
Startup analyses of a megawatt heat pipe cooled reactor12
Effect of fly ash composition and component quantities on the gamma radiation shielding properties of geopolymer12
Solubility, structure transition and chemical durability of Th-doped Nd2Zr2O7 pyrochlore11
A comparison of spent resin degradation by Fenton and O3-Fenton process11
Numerical analysis of heat transfer enhancement of fluid past an oscillating circular cylinder in laminar flow regime11
Characteristics and optimation of heat pipe radiator for space nuclear propulsion spacecraft11
Investigation of hybrid nanofluids effects on heat transfer characteristics in VVER-1000 nuclear reactor11
Numerical study on oscillation characteristics of large chugging of direct condensation of steam in a Tee junction with flowing sub-cooled water11
Comparison of local and global sensitivity analysis methods and application to thermal hydraulic phenomena11
Modeling and simulation of onset of condensation-induced water hammer11
Expert judgement-based risk factor identification and analysis for an effective nuclear decommissioning risk assessment modeling11
Investigations on the gamma-ray shielding performance of green concrete using theoretical, experimental and simulation techniques11
Modified austenitic stainless-steel alloys for sheilding nuclear reactors11
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects11
Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network11
The development of future options for aqueous recycling of spent nuclear fuels11
Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels11
Design of fractional-order NPID controller for the NPK model of advanced nuclear reactor11
A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor11
Low-level radioactive waste management using microwave technology11
Simultaneous estimation of fluid temperature and convective heat transfer coefficient by sequential function specification method11
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D11
Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties11
A multi-level fuzzy switching control method based on fuzzy multi-model and its application for PWR core power control10
Turbulence dissipation of leakage flow in supercritical CO2 labyrinth seals10
Fuel reloads optimization for TRIGA research reactor using Genetic Algorithm coupled with neutronic and thermal-hydraulic codes10
Mixed-oxide fuel strategies in an integral pressurized water reactor10
A multiscale data reconciliation approach for sensor fault detection10
The technology of shielding design for nuclear reactor: A review10
Development of a concept power plant using a Small Modular Reactor coupled with a Supercritical<10
Experimental research on aerosol deposition phenomenon in single-sized rising bubble10
Evaluating urban resilience in a disruptive radioactive event10
Exploring the radiation shielding properties of B2O3-SiO2-ZnO-Na2O-WO3 glasses: A comprehensive study on mechanical, gamma, and neutron attenuation characteristics10
Influence of corium temperature, concrete composition and water injection time on concrete ablation during MCCI: New insights10
Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal10
A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics10
Young Chinese people's perceptions of nuclear power: Connection with enthusiasm for information, perceptions of nuclear reactor technology and NIMBY10
Development and application of hybrid teaching-learning genetic algorithm in fuel reloading optimization10
Analysis of load-following operation characteristics of liquid fuel molten salt reactor10
Radiation shielding performance for local granites10
Evaluation of optimized machine learning models for nuclear reactor accident prediction10
High-temperature mechanical properties of low-carbon steel used for the manufacture of core catcher vessel10
Reliability analysis of passive systems: An overview, status and research expectations10
Applications of Soft Computing in nuclear power plants: A review10
An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction10
Status, opportunities, and challenges of nuclear power development in Sub-Saharan Africa: The case of Ghana10
Diagnosis of break size and location in LOCA and SGTR accidents using support vector machines10
Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application10
Influence of Passive Containment Cooling System on containment thermal hydraulic transients during a postulated severe accident10
CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined10
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Power transient identification10
Hybrid IACO-A*-PSO optimization algorithm for solving multiobjective path planning problem of mobile robot in radioactive environment10
APERTRACK: A particle-tracking model to simulate radionuclide transport in the Arabian/Persian Gulf10
Methods and system for siting advanced nuclear reactors and evaluating energy policy concerns10
A detailed design for a radioactive waste safety management system using ICT technologies10
Measurement of mass attenuation coefficient and its derivable in polymers9
Prediction of 3D natural convection heat transfer characteristics in a shallow enclosure with experimental data9
JSIR2S code for delayed radiation simulations: Validation against measurements at the JSI TRIGA reactor9
Maximizing the use of hydrogen as energy vector to cover the final energy demand for stand-alone systems, application and sensitivity analysis for the Canary Archipelago by 20409
Non-linear analysis of the Density-Wave Oscillations and Ledinegg Instability in heated channel at supercritical condition9
Synthesis and characterization of rare-earth doped aluminium phosphate glasses9
The development of ARSAC for modeling nuclear power plant system9
Effect of bismuth oxide nanoparticles on the radiation shielding of bentonite clay using Fluka modeling calculations and simulation studying9
Early-stage corrosion behavior of Al-based Gd2O3–W shielding composites in a simulated spent fuel wet storage environment9
Atoms for electricity generation in Africa: Analysis of factors affecting the continent's readiness9
Development of ANN structural optimization framework for data-driven prediction of local two-phase flow parameters9
Novel scintillation properties by entrapping ZnO: Ga nanocrystals in epoxy polymer9
Sensitivity analysis of gamma-ray shielding characteristics to the TiO2 concentration in the Bi2O3–ZnO–Pb3O4–Al2O3 glass sample based on the Monte Carlo method9
Refinement of optical/structural features and neutron/gamma-ray protecting capability of P2O5–Li2O–BaO phosphate glass system by adding Bi2O39
The influence of heating on mechanical and nuclear properties of reactive powder concrete as a protective shield in nuclear facilities9
Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method9
Pyrogenic carbon for decontamination of low-level radioactive effluents: Simultaneous separation of 137Cs and 60Co9
Optimization of synthesis conditions for preparation of radiation grafted polymeric fibers and process variables of adsorption with response surface methodology9
Study on the influence of droplet agglomeration on the removal of aerosol by spray system9
Study on water level control system of natural circulation steam generator9
Calcium silicate phosphate cement with samarium oxide additions for neutron shielding applications in nuclear industry9
Simulation of activated corrosion product activity in Korean design system-integrated modular advanced reactor (SMART) under steady-state flow and linearly accelerated corrosion9
Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review9
Gamma radiation attenuation characteristics of polyimide composite with WO29
MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant9
Examine the possibility of increasing the plutonium incineration rate in the current operating pressurized water reactor9
Methodology for inferring reactor core power distribution from an optical fiber based gamma thermometer array9
Development and verification of helium–xenon mixture cooled small reaction system9
Numerical study on inter-wrapper flow and heat transfer characteristics in liquid metal-cooled fast reactors9
Experimental investigation of liquid entrainment in vertical upward annular flow based on fluorescence imaging9
Visual experimental study on bubble characteristics near the heating wall in subcooled flow boiling8
The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs8
Licensing small modular reactors: A state-of-the-art review of the challenges and barriers8
Gamma and neutron attenuation characteristics of bricks containing zinc extraction residue as a novel shielding material8
Reduced order modeling for coupled thermal-hydraulics and reactor physics problems8
Investigation on heat transfer characteristics of Pb–Bi/S–CO2 PCHE with different channel structures8
A study on nuclear hydrogen production using a novel approach cobalt-chlorine thermochemical cycle in a laser driver fission fusion blanket for various molten salt fuels8
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows8
Experimental study on flow patterns in narrow rectangular channels8
Structure and gamma-ray attenuation capabilities for eco-friendly transparent glass system prepared from rice straw ash8
Study of mechanical, thermal, and nuclear radiation attenuation properties of tourmaline loaded heavy weight heat resistant concrete as reactor shielding materials8
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