Nuclear Materials and Energy

Papers
(The TQCC of Nuclear Materials and Energy is 4. 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 2022-05-01 to 2026-05-01.)
ArticleCitations
Study on damage behavior of the outer horizontal target in the EAST lower divertor after plasma operations57
SOLEDGE3X integrated core-edge modelling of tungsten sources, migration, and radiation in WEST plasmas56
Comparative analysis of low cycle fatigue behavior of pre-corroded standard and sub-sized EUROFER97 specimens exposed to ceramic breeder environment37
Effect of hydrogen atoms adsorption on the work function of the LaB637
Corrigendum to “Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis” [Nucl. Mater. Energy 31 (2022) 101160]25
Fission products Sr and Ba in actinide (U, Th) chloride systems: Thermodynamic modelling, experimental investigation and application calculations22
Study on the influence of boronization on the first mirror unit in EAST19
Normal high velocity solid dust impacts on tiles of tokamak-relevant temperature18
A comparative study on the microstructure and performance stability of Cu-Al2O3 and Cu-Y2O3 alloys after high-temperature annealing18
First ion temperature measurements in the MAST-U divertor via Retarding Field Energy Analyzer17
Boundary plasma studies for a spherical tokamak with lithium walls17
Multi-staged ERO2.0 simulation of material erosion and deposition in recessed ITER mirror assemblies17
Quantitative characterization of deuterium and helium retention in the marked tiles with various materials exposed to HL-2A tokamak17
High-temperature tensile and thermal shock characterization of low-temperature rolled tungsten16
Microstructure and high temperature mechanical properties of the new cladding steel of 15Cr-15Ni-Ti-Y16
Impact of water ingress on deuterium release, oxidation, and dust generation in beryllium plasma-facing components16
Slow strain rate testing of Fe-10Cr-4Al ferritic steel in liquid lead and lead–bismuth eutectic16
First-principles study of helium behaviors in oxide dispersion strengthened nickel alloys16
Crystallographic characterization of U2CrN3: A neutron diffraction and transmission electron microscopy approach15
Activated sintering effect of Fe element on tungsten via spark plasma sintering15
A first study of the complex-concentrated-alloy W38Ta36Cr15V11 in Pisces-RF high-flux deuterium plasma14
Erosion of thin boron films at the linear plasma device PSI-2 during deuterium discharges: Atomic and molecular spectroscopy of boron14
The angle of incidence dependence of the sputtering energy threshold of tungsten in future nuclear fusion device13
Evolution of elemental depth profiles on co-deposited layers at the divertor region of the WEST tokamak during its Phase 1 operations13
Influence of 2 (wt%) titanium addition on the oxidation resistance of tungsten12
Determination of Tritium-Helium-3 differential cross-section in the energy range between 0.6 MeV and 3.3 MeV for tritium depth profiling in solids12
Application of an improved WallDYN surface model to estimate ITER boronization layer lifetime12
High-speed camera observation of Hα, Hβ and Hγ associated with mutual neutralization and EIR in GAMMA 10/PDX divertor simulated plasma11
Deuterium retention in pre-lithiated samples and Li–D co-deposits in the DIII-D tokamak11
First-principles study of beryllium thermodynamics and clustering mechanism in molybdenum: Effects of vacancies and self-interstitial atoms11
Comparative studies of tungsten erosion and edge transport under partially detached divertor condition of CFETR with neon and argon seedings11
In-situ observation of restoration of tungsten plate via high-temperature confocal laser scanning microscopy11
Instability of molten beryllium layers during ITER thermal quenches11
Ion-irradiation effect on swelling and microstructure of BN particle dispersed liquid phase sintering SiC11
Production of 99Mo at IFMIF-DONES reusing the flux of neutrons11
Modeling intrinsic- and displacement-damage-driven retention in EUROFER11
Sputtering fabrication of isolated W nanocolumns: A possible alternative as plasma facing material for nuclear fusion reactors11
Thermal hydraulic and structural analysis of the IFMIF-DONES liquid-lithium target system11
CIEMAT experimental proposal on lithium ignition in support of DONES licensing (LiFIRE facility)10
Editorial for proceedings of ICFRM-2010
Studies of material deposition during boronization using quartz crystal microbalance in EAST10
Laser-induced breakdown spectroscopy for helium detection in beryllium coatings10
Pronounced inhibitory mechanism of Cr on vacancy-like defects in Fe9Cr alloy irradiation with helium ions10
Microstructure and mechanical properties of Bp/Al neutron shielding composites10
Validation of EDGDE2D-EIRENE predicted 2D distributions of electron temperature and density against divertor Thomson scattering measurements in the low-field side divertor leg in DIII-D10
Reaction–diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, II: Array of cavities10
Real-time helium bubble growth in tungsten by in-situ GISAXS10
2D GEM-based SXR imaging diagnostics for plasma radiation: Preliminary design and simulations10
A new attempt to further reduce the work function of the cesiated surface: The strongest electronegative element fluorine co-adsorption with cesium on Mo (001) surface10
Observation of the significant reductions of electron density and electron temperature in a cascaded arc high density argon plasma with ammonia seeding comparing with nitrogen seeding by laser Thomson10
Preliminary study on the microstructure and hardness of wire and arc additively manufactured ODS-RAFM steel subjected to 2.5 MeV Fe ion irradiation10
Corrigendum to “The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation” [Nucl. Mater. Energy 210
Recollections for the 50th anniversary of the plasma surface interactions (PSI) in controlled fusion devices conference10
Exposure of tungsten heavy alloys at high thermal loads in LHD9
Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES9
Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy9
Multi-Scale microscopy of Reactive sintered boride (RSB) neutron shielding materials9
13C surface characterization of midplane and crown collector probes on DIII-D9
Understanding the oxidation of pure tungsten in air and its impact on the lifecycle of a fusion power plant9
Design of a multi-configurations divertor for the DTT facility9
Experiment-modeling studies comparing energy dissipation in the DIII-D SAS and SAS-VW divertors9
Low-dose damage evolution in pure magnesium under electron irradiation: Effect of foil orientation and pre-existing dislocations9
Simulation of loss-of-coolant accident with thin-walled cladding tubes9
Physics of the electric field in the scrape-off layer in ASDEX Upgrade L-mode discharges and comparison to experiments8
Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments8
Fe-ion irradiation induced changes in precipitates of 11Cr ferritic/martensitic steel8
Investigating the stability and work function effects of Ba atoms adsorption on the Mo (110) surface8
Assessment of the ITER divertor bolometer diagnostic performance8
Nanostructure formation and D retention in redeposited-like W exposed to linear plasmas8
Study on photoluminescence properties of Er2O3 materials as irradiation damage and temperature sensors8
Tribological and microstructure evaluation of 17Cr ferritic ODS steel fabricated through vacuum hot pressing8
Deuterium retention and transport in ion-irradiated tungsten exposed to deuterium atoms: Role of grain boundaries8
Comparative analysis of gas release from biphasic lithium ceramics pebble beds of various pebbles sizes and content under neutron irradiation conditions8
Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis8
Modification of chemical and mechanical properties of p-W-O coating after Magnum-PSI D2-N2 plasma exposure and its consequences for the analysis of LIBS spectra8
Effects of minor rhenium additions on the thermal properties and recrystallization temperature of tungsten alloy8
Effects of thermal aging at 873 K on the impact properties of an ODS ferritic steel8
First principles investigation of adsorption and diffusion behavior of fission products (Cs, Sr and I) on carbide ceramic (SiC, NbC and ZrC) coatings8
Preparation and characterization of marker graphite tiles for PWI research of HL-38
Removal of deuterium retention by various helium discharge cleanings under strong magnetic field in EAST superconducting tokamak8
Operating voltage of a W-fuzz cathode arc and the mass/charge composition of the arc plasma depending on the fuzz thickness8
Analysis of edge transport in L-mode negative triangularity TCV discharges8
Collisional-Radiative modeling of unresolved transition array spectra near 200 Å from W17+-W25+ emissions for diagnostics of ITER edge plasma8
Uniaxial strain-induced cascade defect evolution in molybdenum: An atomistic study with a new machine-learning potential8
Microstructure of tungsten coatings effect on deuterium plasma-driven permeation through RAFM steel8
Simulation study of the influence of the outer target geometry on tungsten contamination: Horizontal vs. vertical target8
Effect of nanosecond laser irradiation on tungsten grain structure8
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method8
Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials8
Predicting image processing-normalized DL-EPRT performance from Rudimentary Cihal method-based counterpart8
Coexistence of H-MAR and N-MAR in divertor simulation experimental module of GAMMA 10/PDX8
Design of a two-stage cryopump with hydrogen-helium separation capability for fusion reactor application7
Heterogeneous microstructure and anisotropic mechanical properties of reduced activation ferritic/martensitic steel fabricated by wire arc additive manufacturing7
Grain orientation and temperature dependences of bubbles at tungsten surfaces upon helium plasma exposure7
Quantification of the uncertainty arising from atomic physics in edge plasmas7
Measurement of thermal expansion anisotropy in Be12Ti and Be12V7
Positron annihilation studies of Eurofer97/ODS steels after helium ion implantation7
Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel7
Effect of nickel on the FeCrAl alloy oxidation resistance in steam environment at high temperature (1000 °C)7
Transport in the tokamak - reactor edge plasma with strong collisionality7
EDGE2D-EIRENE and ERO2.0 predictions of nitrogen molecular break-up and transport in the divertor of JET low-confinement mode plasmas7
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms7
Subtle microstructural changes during prolonged annealing of ODS-Eurofer steel7
New evaluation of neutron-induced displacement damage cross section for EUROFER977
Visualizing spatially inhomogeneous hydrogen isotope diffusion by hydrogenography7
Tight-binding potential model for Re and W-Re alloy6
Validating reduced models for detachment onset and reattachment times on MAST-U6
Effective control of intrinsic impurities using n = 1 resonant magnetic perturbation (RMP) in EAST H-mode plasma6
Reduction of MHD pressure drop by electrical insulating oxide layers in liquid breeder blanket of fusion reactors6
A study on initial formation stage of proton irradiation defects in reactor pressure vessel steel6
First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility6
First study of the location of deuterium in displacement-damaged tungsten by nuclear reaction analysis in channeling configuration6
Investigation of the deposition behaviour of cobalt on 304 stainless steel in a simulated spent nuclear fuel pool6
Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: A numerical simulation investigation6
Molecular dynamics study of interstitial He clusters in nickel6
Characterization of the peak temperature on upper W divertor target during D and He plasma discharges in EAST6
First in operando transient grating spectroscopy measurements on tungsten during high flux plasma operation in PISCES-RF6
Paramagnetic radiation-induced defect centres and their correlation with the optical properties of irradiated advanced ceramic breeder pebbles6
Segregation of alloying elements at the TiC/V interface: A first-principles study6
Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400 – 900 °C6
Study of line spectra emitted by hydrogen isotopes in tokamaks through Deep-Learning algorithms6
Efficiency evaluation of fuel retention diagnostic in first wall by LID-QMS: Based on LIBS6
Alkaline hydrothermal treatment of P25 titanium dioxide for low temperature sintering of Li2TiO3 tritium breeding ceramics6
Editorial for the Special Issue on EUROFER976
The effect of CD4 injection on WD molecule sputtering at the divertor target in EAST6
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating6
Simulations of beryllium castellation gap bridging during vertical displacement events6
Effects of Cr and Si addition on the high-temperature oxidation resistance in high-Mn alumina-forming oxide dispersion strengthened austenitic steels6
Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices6
Investigation of particle exhaust from EAST divertor6
The effects of W and Mo on the formation of early stage α’ solute clusters in ion-irradiated Fe-Cr-X (X = W/Mo) alloys6
Role of doped ZrC on deuterium trapping in W-ZrC alloy6
Additive manufacturing of FeCrAl alloys for nuclear applications - A focused review6
Stress distribution in a 316L(N) steel narrow gap TIG model weld for Gen IV nuclear applications6
Effect of electronic excitations on hydrogen behavior in tungsten6
Influence of surface morphology on erosion of plasma-facing components in H-mode plasmas of ASDEX Upgrade6
Mechanical and microstructural analysis of tungsten exposed in JET deuterium plasmas6
Effects of helium implantation on the deuterium permeation behavior in oxidized Fe-Cr-Al ferritic steel6
Fuel recycling control in long pulse operation with full tungsten divertors in EAST tokamak6
Preliminary numerical study on thermal impact of runaway electrons to limiter PFU in fusion reactor6
Lyman line opacities in tokamak divertor plasmas under high-recycling and detached conditions6
Deuterium retention in self-irradiated tungsten by D2 gas loading6
Densification behavior of ceramic tritium breeder pebble beds under vertical vibration: Effect of vibration parameters6
Optimally incorporating intra-cascade spatial correlations into mean-field cluster dynamics for radiation damage modeling6
Innovative laser-based methods for monitoring fuel retention in ITER6
Effect of boron on the microstructure and performance of HIP-prepared high boron steels6
Cold plasma studies on the influence of surface microstructured thickness in the secondary electron emission from tungsten coatings5
Crystal-orientation-dependent physical sputtering from four elemental metals5
Effect of spatial distribution of impurity ions on the signal of ‘C/O monitor for Wendelstein 7-X’ - an indicator of plasma wall interactions5
HEAT simulation and IR data comparison for ST40 plasma-facing components5
Material transport from marker tiles in the JET divertor5
Effect of Si and Nb additions on carbonitride coatings under proton irradiation: A comprehensive analysis of structural, mechanical, corrosion, and neutron activation properties5
Spinodal decomposition and radiation damage of a FeCuMnNi high-entropy alloy5
Asymmetry in particle load on divertor tiles in different magnetic field configurations of LHD5
Heterogenous microstructure and texture evolution of K-doped tungsten thick plate during hot-rolling processing5
Influence of initial damage distribution and sinks in fusion materials: A parametric OKMC study of W vs Fe5
Erosion and redeposition patterns on divertor tiles after exposure in the first operational phase of WEST5
Overview of advanced plasma-facing materials testing for Fusion Pilot Plants at DIII-D5
Long-term thermal stability of biphasic Li4SiO4-Li2TiO3 EU reference tritium breeder ceramics enriched in Li-65
The microstructure and He+ ion irradiation behavior of novel low-activation W-Ta-Cr-V refractory high entropy alloy for nuclear applications5
Effect of 5 MeV Au3+ ions irradiation damage on surface blistering and deuterium retention behaviors in W and W-ZrC alloy5
Study on corrosion behavior of China low activation ferritic/martensitic steel in static liquid lithium5
Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron5
Stress analysis of aspherical TRISO-coated particle with X-ray computed tomography5
Stabilization of liquid tin surfaces under D plasma irradiation by a capillary porous system5
Variation in the volumetric power and momentum losses in the JET-ILW scrape-off layer5
Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code5
Evolution of He bubbles during the steam oxidation in He-implanted ferritic-martensitic steels5
Direct experimental measurement of the solubility of hydrogen isotopes in the Eurofer-97 RAFM5
Review on ASDEX Upgrade operation with tungsten plasma facing components5
Helium swelling behavior for neutron multipliers after irradiation with He ions at high temperatures5
First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall5
Low temperature hydrogen superpermeation in vanadium composite metal foil pumps5
Pisces-RF: A helicon-plasma based linear-device for the study of fusion relevant plasma-materials-interactions5
First-principles study on the hydrogen trapping by vacancy and substitutional helium in W–Ta alloy5
Densification Behaviors of Zirconium Carbide with Silicon Additive Produced by Spark Plasma Sintering5
The effect of D25
Beryllium intermetallics: Industrial experience on development and manufacture5
Hydrogen trapping in vanadium carbide alloyed with transition metals5
Improved Coulomb collision operator for kinetic ion transport with EMC3-EIRENE simulating Nitrogen seeding in medium density ITER L-mode scenario5
A First-principles analysis of Structural, Electronic, Elastic, and vacant properties of BCC, FCC and HCP tungsten at different electronic temperatures5
Non-destructive characterization of advanced nuclear fuel materials using neutron imaging5
First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor5
Deuterium permeation and retention behavior in copper-based brazing filler materials4
Bidirectional reflectance distribution function of recrystallized tungsten mono-block exposed to cyclic heat loading4
Simultaneous characterization of O, C, 6Li, and medium-weight impurities concentration in PbLi by ion beam analysis4
Influence of redeposited tungsten and EUROFER97 layers on deuterium retention in plasma-facing materials4
Numerical modeling of impurity powder injection in W7-X4
Detachment scalings derived from 1D scrape-off-layer simulations4
Phase-field simulations of the recrystallization and the mechanical property response in deformed tungsten4
Effect of the heating rate and Y2O3 coating on the microstructure of Wf/Y2O3/W composites via field assisted sintering technology4
Influence of the distance of a collisional cascade to an edge dipole in α4
DEM study on the force chain evolution of biaxial compression of pebble bed4
Electron beam welding behavior in Eurofer subjected to the PbLi eutectic4
Novel criterion for W-Cu interlayer joint delamination in divertor target monoblock under heating through ANSYS-CZM parametric studies4
High temperature tensile and creep properties of the new cladding steel of 15-15Ti-Y4
Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization4
A new method for preparing high-quality and fatigue-resistant divertor W/Cu joints4
SLM-printed EUROFER steel for fusion applications4
Post-mortem analysis of material deposition and fuel retention on the plasma-facing materials after the 2021 campaign in EAST4
Microstructure, mechanical properties and corrosion behavior of W-B-Ni-Fe shielding cermets synthesized by reactive boride sintering4
Three-dimensional structure of radiative cooling in impurity seeded plasmas in the Large Helical Device4
Modeling input to the ITER glow discharge boronization system design4
Advanced materials to enhance the nuclear performances of the high temperature Dual Coolant Lithium lead breeding blanket for the EU DEMO4
Study the erosion of Eurofer-97 steel with the linear plasma device GyM4
Melting behaviour of mixed plutonium and iron oxides: An experimental study4
Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade4
Radiation characteristics of detached divertor plasmas in W7-X4
First-principles study on thermal expansion of W-Re sigma and chi phases4
A new design concept of actively cooled plasma-facing units for the divertors of fusion reactors4
Study on the adsorption mechanism and properties of silver-loaded zeolite for radioactive iodine4
Advancement of strength and toughness in ultra-low carbon martensitic stainless steel by reversed austenite4
Investigating the microstructure of additively manufactured tungsten parts produced by electron beam powder bed fusion process4
Theoretical prediction of high temperature mechanical, thermodynamic and surface O adsorption properties of W-Cu alloys: Advanced high temperature super strength alloy materials4
Thick functionally-graded W-316L composite coatings for nuclear fusion applications4
Microstructural insights into EUROFER97 batch 3 steels4
Evaluation of neutron irradiation-induced displacement damage in heat pipe reactor4
Coexistence of He and H in ceramic insulators for the DCLL Breeding Blanket: Evaluation of potential synergistic effects by TEM and nanoindentation4
Boron layer preparation, characterization and hydrogen isotope permeability for fusion application4
TALIF measurements of atomic deuterium in toroidal divertor simulator NAGDIS-T4
Study on the annealing and three-point bending fracture behavior of single W fiber-reinforced W composites with multiple interfaces prepared by CVD4
New processing routes for Zr-based ODS ferritic steels4
Positron lifetime study of ion-irradiated tungsten: Ion type and dose effects4
Corrigendum to “Microstructural study of the thermal stability of a thermomechanically treated T91 steel by TEM in situ annealing” [Nucl. Mater. Energy 32 (2022) 101213]4
A percolation theory-based approach for analyzing fluid flow mechanism in blanket pebble beds4
Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor4
Numerical analysis of recrystallization behaviors for W monoblock under cyclic high heat flux4
Improving accuracy in fluoride salt composition analysis: A focus on sample preparation for ICP-MS4
Exploring the impacts of Li and He impurities in a tungsten matrix: A First-Principles study4
First principles investigation of the electronic-thermal transport of ThN, UN, and ThC4
Divertor erosion at ASDEX Upgrade during helium plasma operations4
Effect of temperature on intermetallic compound formation and mechanical properties of Mo/BNi2/304L vacuum brazed joints4
Assessing the toroidal radiation distribution at Wendelstein 7-X by combining Gaussian Process Tomography and field line mapping4
Study of irradiation-induced vacancy-type defects in tungsten using positron annihilation spectroscopy4
Deuterium plasma exposure of thin oxide films on tungsten - oxygen removal and deuterium uptake4
ERO2.0 modelling of divertor marker erosion in ASDEX Upgrade L-mode experiments4
Recent progress in research on bonding technologies of W/Cu monoblocks as the divertor for nuclear fusion reactors4
Collector probe analysis of tungsten transport to the far-SOL from the DIII-D SAS-VW divertor experiment4
Deuterium retention characteristics during lithium powder and granule injection in EAST4
Phase transition behaviour and properties of Ti-Gd based thermal neutron shielding alloys4
Sputtering yield reduction for nano-columnar W surfaces under D ion irradiation4
High heat flux testing of wire-based laser metal deposition coated plasma-facing components4
Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution4
Effect of dispersion particles and precipitates on the corrosion properties of ODS-Cu, Cu-Cr-Zr and Cu-Cr alloys in Na2SO4 solutions4
Edge plasma turbulence simulations in detached regimes with the SOLEDGE3X code4
Effect of molybdenum release on UO2/MOX fuel oxidation under severe light water reactor accident conditions4
Investigation of thermoplastic deformation behavior and microstructural evolution of CLF-1 steel for fusion blankets4
Assessment of carbon net erosion/deposition at the divertor of W7-X4
Utilization of D2 molecular band emission for electron density measurement4
Numerical study of fully baffled Super-X L-mode discharges on TCV4
0.36412596702576