Nuclear Materials and Energy

Papers
(The TQCC of Nuclear Materials and Energy is 3. 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 2021-05-01 to 2025-05-01.)
ArticleCitations
Multi-staged ERO2.0 simulation of material erosion and deposition in recessed ITER mirror assemblies38
High-temperature tensile and thermal shock characterization of low-temperature rolled tungsten30
Effects of microstructural anisotropy and helium implantation on tensile properties of powder-metallurgy processed tungsten plates28
Irradiation effects in tungsten—From surface effects to bulk mechanical properties28
Activated sintering effect of Fe element on tungsten via spark plasma sintering27
Microstructure and high temperature mechanical properties of the new cladding steel of 15Cr-15Ni-Ti-Y26
First-principles study of helium behaviors in oxide dispersion strengthened nickel alloys22
SOLEDGE3X integrated core-edge modelling of tungsten sources, migration, and radiation in WEST plasmas21
Impact of water ingress on deuterium release, oxidation, and dust generation in beryllium plasma-facing components21
Normal high velocity solid dust impacts on tiles of tokamak-relevant temperature21
Comparative analysis of low cycle fatigue behavior of pre-corroded standard and sub-sized EUROFER97 specimens exposed to ceramic breeder environment21
Corrigendum to “Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis” [Nucl. Mater. Energy 31 (2022) 101160]19
Study on damage behavior of the outer horizontal target in the EAST lower divertor after plasma operations18
A comparative study on the microstructure and performance stability of Cu-Al2O3 and Cu-Y2O3 alloys after high-temperature annealing18
Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment16
Crystallographic characterization of U2CrN3: A neutron diffraction and transmission electron microscopy approach15
Quantitative characterization of deuterium and helium retention in the marked tiles with various materials exposed to HL-2A tokamak15
An examination of the Neutral Penetration Model1/n15
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 214
Slow strain rate testing of Fe-10Cr-4Al ferritic steel in liquid lead and lead–bismuth eutectic14
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) surface14
Boundary plasma studies for a spherical tokamak with lithium walls14
Ion-irradiation effect on swelling and microstructure of BN particle dispersed liquid phase sintering SiC14
Wall conditioning and ELM mitigation with boron nitride powder injection in KSTAR13
Instability of molten beryllium layers during ITER thermal quenches12
Microstructure and mechanical properties of Bp/Al neutron shielding composites12
Low-dose damage evolution in pure magnesium under electron irradiation: Effect of foil orientation and pre-existing dislocations12
A method for high heat flux fatigue test of W/Cu/steel small mock-up using normal cooling conditions12
Real-time helium bubble growth in tungsten by in-situ GISAXS11
Modeling intrinsic- and displacement-damage-driven retention in EUROFER11
Comparative studies of tungsten erosion and edge transport under partially detached divertor condition of CFETR with neon and argon seedings11
CIEMAT experimental proposal on lithium ignition in support of DONES licensing (LiFIRE facility)10
Pronounced inhibitory mechanism of Cr on vacancy-like defects in Fe9Cr alloy irradiation with helium ions10
2D GEM-based SXR imaging diagnostics for plasma radiation: Preliminary design and simulations10
Preliminary study on the microstructure and hardness of wire and arc additively manufactured ODS-RAFM steel subjected to 2.5 MeV Fe ion irradiation10
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 solids10
Production of 99Mo at IFMIF-DONES reusing the flux of neutrons10
Effects of ball size and microstructures on indentation curves of Fe9Cr model alloys and tempered martensitic steel Eurofer9710
Transient interactions of boron carbide with molten uranium oxide10
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
Reaction–diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, II: Array of cavities10
Thermal hydraulic and structural analysis of the IFMIF-DONES liquid-lithium target system9
Influence of 2 (wt%) titanium addition on the oxidation resistance of tungsten9
Ab initio modelling of intergranular fracture of nickel containing phosphorus: Interfacial excess properties9
Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments9
Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets9
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-D9
Sputtering fabrication of isolated W nanocolumns: A possible alternative as plasma facing material for nuclear fusion reactors9
Editorial for proceedings of ICFRM-209
Laser-induced breakdown spectroscopy for helium detection in beryllium coatings9
In-situ observation of restoration of tungsten plate via high-temperature confocal laser scanning microscopy9
The angle of incidence dependence of the sputtering energy threshold of tungsten in future nuclear fusion device9
High-speed camera observation of Hα, Hβ and Hγ associated with mutual neutralization and EIR in GAMMA 10/PDX divertor simulated plasma9
Assessment of the ITER divertor bolometer diagnostic performance8
13C surface characterization of midplane and crown collector probes on DIII-D8
Comparative analysis of gas release from biphasic lithium ceramics pebble beds of various pebbles sizes and content under neutron irradiation conditions8
Effects of minor rhenium additions on the thermal properties and recrystallization temperature of tungsten alloy8
Assessment of plasma power deposition on the ITER ICRH antennas8
Design of a multi-configurations divertor for the DTT facility8
In-situ observation of damage structure in Cu-Cr-Zr and Cu-Cr alloy during 1.25 MeV electron irradiation8
Analysis of edge transport in L-mode negative triangularity TCV discharges8
Annihilation kinetics of irradiation defects in promising tritium breeding pebbles8
Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis8
Physics of the electric field in the scrape-off layer in ASDEX Upgrade L-mode discharges and comparison to experiments8
Effects of thermal aging at 873 K on the impact properties of an ODS ferritic steel8
Multi-Scale microscopy of Reactive sintered boride (RSB) neutron shielding materials8
Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES8
Microstructure of tungsten coatings effect on deuterium plasma-driven permeation through RAFM steel8
Experiment-modeling studies comparing energy dissipation in the DIII-D SAS and SAS-VW divertors8
Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy7
Collisional-Radiative modeling of unresolved transition array spectra near 200 Å from W17+-W25+ emissions for diagnostics of ITER edge plasma7
Assessment of laser induced breakdown spectroscopy accuracy for determination of hydrogen accumulation in tungsten7
Subtle microstructural changes during prolonged annealing of ODS-Eurofer steel7
Deuterium retention and transport in ion-irradiated tungsten exposed to deuterium atoms: Role of grain boundaries7
Investigation on tritium retention and surface properties on the first wall in the large helical Device7
Study on photoluminescence properties of Er2O3 materials as irradiation damage and temperature sensors7
Simulation study of the influence of the outer target geometry on tungsten contamination: Horizontal vs. vertical target7
EDGE2D-EIRENE and ERO2.0 predictions of nitrogen molecular break-up and transport in the divertor of JET low-confinement mode plasmas7
Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel7
Positron annihilation studies of Eurofer97/ODS steels after helium ion implantation7
Coexistence of H-MAR and N-MAR in divertor simulation experimental module of GAMMA 10/PDX7
Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials7
Simulation of loss-of-coolant accident with thin-walled cladding tubes7
Nanostructure formation and D retention in redeposited-like W exposed to linear plasmas7
Transport in the tokamak - reactor edge plasma with strong collisionality7
Exposure of tungsten heavy alloys at high thermal loads in LHD7
Re-deposition of ITER-grade Be on plasma gun facility QSPA-Be: Characterization & plasma cleaning7
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method7
Effect of nanosecond laser irradiation on tungsten grain structure7
Effects of Cr and Si addition on the high-temperature oxidation resistance in high-Mn alumina-forming oxide dispersion strengthened austenitic steels6
Effect of boron on the microstructure and performance of HIP-prepared high boron steels6
Heterogeneous microstructure and anisotropic mechanical properties of reduced activation ferritic/martensitic steel fabricated by wire arc additive manufacturing6
Removal of deuterium retention by various helium discharge cleanings under strong magnetic field in EAST superconducting tokamak6
Arc behaviour on different materials in ASDEX Upgrade6
Visualizing spatially inhomogeneous hydrogen isotope diffusion by hydrogenography6
Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy6
Comparison of a collisional-radiative fluid model of H2 in UEDGE to the kinetic neutral code EIRENE6
Effect of electronic excitations on hydrogen behavior in tungsten6
Impact of negative triangularity on edge plasma transport and turbulence in TOKAM3X simulations6
Characterization of the peak temperature on upper W divertor target during D and He plasma discharges in EAST6
Measurement of thermal expansion anisotropy in Be12Ti and Be12V6
Predicting image processing-normalized DL-EPRT performance from Rudimentary Cihal method-based counterpart6
Quantification of the uncertainty arising from atomic physics in edge plasmas6
Grain orientation and temperature dependences of bubbles at tungsten surfaces upon helium plasma exposure6
Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: A numerical simulation investigation6
Additive manufacturing of FeCrAl alloys for nuclear applications - A focused review6
Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating6
Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content6
Fuel recycling control in long pulse operation with full tungsten divertors in EAST tokamak6
Operating voltage of a W-fuzz cathode arc and the mass/charge composition of the arc plasma depending on the fuzz thickness6
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms6
Segregation of alloying elements at the TiC/V interface: A first-principles study6
New evaluation of neutron-induced displacement damage cross section for EUROFER976
Convolutional neural networks for the in-situ investigation of blistering on plasma-exposed metal surfaces6
Preparation and characterization of marker graphite tiles for PWI research of HL-36
First study of the location of deuterium in displacement-damaged tungsten by nuclear reaction analysis in channeling configuration6
Study of microscale surface morphology changing of the retroreflector in EAST by means of laser speckle interferometry technique5
Effect of spatial distribution of impurity ions on the signal of ‘C/O monitor for Wendelstein 7-X’ - an indicator of plasma wall interactions5
Asymmetry in particle load on divertor tiles in different magnetic field configurations of LHD5
Mechanical and microstructural analysis of tungsten exposed in JET deuterium plasmas5
Molecular dynamics study of interstitial He clusters in nickel5
Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code5
Stress distribution in a 316L(N) steel narrow gap TIG model weld for Gen IV nuclear applications5
First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility5
Validating reduced models for detachment onset and reattachment times on MAST-U5
Ab initio investigation of properties and mobility of helium defects in La2Sn2O7 pyrochlore5
Reduction of MHD pressure drop by electrical insulating oxide layers in liquid breeder blanket of fusion reactors5
Pisces-RF: A helicon-plasma based linear-device for the study of fusion relevant plasma-materials-interactions5
Helium swelling behavior for neutron multipliers after irradiation with He ions at high temperatures5
Beryllium intermetallics: Industrial experience on development and manufacture5
Stress analysis of aspherical TRISO-coated particle with X-ray computed tomography5
Structural analysis of the Interspace Afocal Module of the Wide Angle Viewing System diagnostic for ITER5
Cold plasma studies on the influence of surface microstructured thickness in the secondary electron emission from tungsten coatings5
CF-LIBS quantification and depth profile analysis of Be coating mixed layers5
Editorial for the Special Issue on EUROFER975
A study on initial formation stage of proton irradiation defects in reactor pressure vessel steel5
Hydrogen trapping in vanadium carbide alloyed with transition metals5
Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature5
First feedback-controlled divertor detachment in W7-X: Experience from TDU operation and prospects for operation with actively cooled divertor5
Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices5
Improved Coulomb collision operator for kinetic ion transport with EMC3-EIRENE simulating Nitrogen seeding in medium density ITER L-mode scenario5
Application of spatially hybrid fluid–kinetic neutral model on JET L-mode plasmas5
A First-principles analysis of Structural, Electronic, Elastic, and vacant properties of BCC, FCC and HCP tungsten at different electronic temperatures5
Multiscale modelling for fusion and fission materials: The M4F project5
Control of deformation and annealing process to produce incoherent Σ3 boundaries in Hastelloy C-276 alloy5
Phase-field simulations of the recrystallization and the mechanical property response in deformed tungsten5
Non-destructive characterization of advanced nuclear fuel materials using neutron imaging5
Crystal-orientation-dependent physical sputtering from four elemental metals5
Investigation on effects of tritium release behavior in Li4SiO4 pebbles5
The microstructure and He+ ion irradiation behavior of novel low-activation W-Ta-Cr-V refractory high entropy alloy for nuclear applications5
Multi-scale fracture probability analysis of tungsten monoblocks under fusion conditions5
Alkaline hydrothermal treatment of P25 titanium dioxide for low temperature sintering of Li2TiO3 tritium breeding ceramics5
First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall5
Spinodal decomposition and radiation damage of a FeCuMnNi high-entropy alloy5
Investigation of particle exhaust from EAST divertor5
Effects of helium implantation on the deuterium permeation behavior in oxidized Fe-Cr-Al ferritic steel5
Lyman line opacities in tokamak divertor plasmas under high-recycling and detached conditions5
Effective control of intrinsic impurities using n = 1 resonant magnetic perturbation (RMP) in EAST H-mode plasma5
The effect of CD4 injection on WD molecule sputtering at the divertor target in EAST5
Variation in the volumetric power and momentum losses in the JET-ILW scrape-off layer5
First-principles study on the hydrogen trapping by vacancy and substitutional helium in W–Ta alloy5
Effect of 5 MeV Au3+ ions irradiation damage on surface blistering and deuterium retention behaviors in W and W-ZrC alloy5
Influence of surface morphology on erosion of plasma-facing components in H-mode plasmas of ASDEX Upgrade5
Irradiation hardening behaviors of large-scale hot rolling potassium-doped tungsten alloy under synergistic irradiations of Fe11+ ion combined with deuterium and helium plasmas5
Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron4
Utilization of D2 molecular band emission for electron density measurement4
Permeation and trapping of hydrogen in Eurofer974
ERO2.0 predictions of nickel migration in the JET ITER-Like Wall4
Numerical analysis of effective thermal conductivity of FCM with multilayer TRISO particle4
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
Study on the adsorption mechanism and properties of silver-loaded zeolite for radioactive iodine4
D retention in e-beam powder-bed fused (3-D printed) tungsten exposed to high-flux deuterium plasma in Pisces-RF4
Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution4
Small punch creep investigation of Eurofer97 and 14Cr oxide dispersion strengthened steel4
Effect of molybdenum release on UO2/MOX fuel oxidation under severe light water reactor accident conditions4
Surface modified-gadolinium/boron/polyethylene composite with high shielding performance for neutron and gamma-ray4
Effect of Si and Nb additions on carbonitride coatings under proton irradiation: A comprehensive analysis of structural, mechanical, corrosion, and neutron activation properties4
Influence of the distance of a collisional cascade to an edge dipole in α4
Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy4
First principles investigation of the electronic-thermal transport of ThN, UN, and ThC4
Surface features of strongly heated bulk tungsten divertor plates at ASDEX Upgrade4
First-principles study on thermal expansion of W-Re sigma and chi phases4
Depth profile CF LIBS analysis of the wall deposited layer in the COMPASS tokamak after LiSn testing campaign4
Microstructural insights into EUROFER97 batch 3 steels4
Study the erosion of Eurofer-97 steel with the linear plasma device GyM4
Sputtering yield reduction for nano-columnar W surfaces under D ion irradiation4
Edge plasma turbulence simulations in detached regimes with the SOLEDGE3X code4
Radiation resistance of single-mode optical fibres with view to in-reactor applications4
The synergy of heavy-ion irradiation and lithium-lead corrosion on deuterium permeation behavior of ceramic coating4
New processing routes for Zr-based ODS ferritic steels4
Low temperature hydrogen superpermeation in vanadium composite metal foil pumps4
HEAT simulation and IR data comparison for ST40 plasma-facing components4
Study on corrosion behavior of China low activation ferritic/martensitic steel in static liquid lithium4
Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST4
Predicting the stability and exploring the fundamental physical properties of tetragonal Gd2O3: A comprehensive first-principles investigation4
Thick functionally-graded W-316L composite coatings for nuclear fusion applications4
Advancement of strength and toughness in ultra-low carbon martensitic stainless steel by reversed austenite4
Three-dimensional structure of radiative cooling in impurity seeded plasmas in the Large Helical Device4
Study of irradiation-induced vacancy-type defects in tungsten using positron annihilation spectroscopy4
Reassessing energy deposition for the ITER 5 MA vertical displacement event with an improved DINA model4
Stabilization of liquid tin surfaces under D plasma irradiation by a capillary porous system4
Liquid lithium divertor analysis using coupled plasma material interaction model4
Numerical modeling of impurity powder injection in W7-X4
Micron-sized dust and nanoparticles produced in the WEST tokamak4
Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor4
Material transport from marker tiles in the JET divertor4
The effect of D24
A novel solution for hydrogen monitoring in fusion processes: 3D printed BaCe0.6Zr0.3Y0.1O3-α sensors3
Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns3
Post-mortem analysis of material deposition and fuel retention on the plasma-facing materials after the 2021 campaign in EAST3
Calculation of in-situ steady-state heat flux on EAST lower divertor3
DEM study on the force chain evolution of biaxial compression of pebble bed3
Effect of initial exposure temperature on the deuterium retention and surface blistering in tungsten3
Influence of the structural state and crystallographic texture of Zr-2.5% Nb alloy samples on the anisotropy of their thermal expansion3
Recent progress in research on bonding technologies of W/Cu monoblocks as the divertor for nuclear fusion reactors3
Studies of the material erosion and deposition during the wall conditioning processes using quartz crystal microbalance in EAST3
Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor3
Comparing lithium vapor box designs in a high heat flux scenario using SOLPS-ITER3
SOLPS-ITER simulations to study the impact of aspect ratio on edge fueling neutrals in tokamaks3
Corrosion behavior of AlCrFeTiNb and AlCrFeTiNb/(AlCrFeTiNb)N coatings in flowing lead–bismuth eutectic alloy with saturated oxygen concentration at 550 ℃3
Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation3
Divertor closure effects on the TCV boundary plasma3
Modelling the PbLi flow including tritium transport and permeation with GETTHEM3
Theoretical prediction of high temperature mechanical, thermodynamic and surface O adsorption properties of W-Cu alloys: Advanced high temperature super strength alloy materials3
Mechanical characterization of the stainless steel welds for the JT-60SA Cryostat Vessel Body Cylindrical Section3
Theoretical investigation of structural, electronic, mechanical, surface work function and thermodynamic properties of La1-xMxB6 (M = Ba, Sr, Ca) compounds: Potential plasma grid materials in N-NBI sy3
Deuterium permeation and retention behavior in copper-based brazing filler materials3
Comparative study of microstructural evolution in W-3Re alloy under high-temperature conditions: High heat flux loading versus furnace heating3
Developing deep learning algorithms for inferring upstream separatrix density at JET3
Investigating the role of divertor geometry on density build-up in the island divertor3
Tungsten fuzz growth at low temperatures (<900 K) on a surface with nanocones3
Experimental investigation of the impact of irradiation damages on the mechanical properties of tungsten3
Ab-initio simulations of atomic hydrogen interaction with Nb and V at clean and oxygen covered surfaces3
Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation3
Effect of edge plasma density on hot spot in LHCD plasma in EAST3
Stability of beryllium-tungsten coatings under annealing up to 1273 K3
Garnet-type lithium sensors for the monitoring and control of Pb-Li alloys in tritium breeding modules3
Molecular dynamics simulation of displacement cascades in cubic silicon carbide3
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors3
Evaluation of neutron irradiation-induced displacement damage in heat pipe reactor3
In situ study of thermal shock damage to high-temperature ceramics3
An approximate in-situ method for investigating irradiation damage of grain boundary3
A new design concept of actively cooled plasma-facing units for the divertors of fusion reactors3
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-3
Controlling intermetallics formation at V-4Cr-4Ti/316SS laser-welded joint3
Geometries, electronic structures, mechanical properties and stabilities of Fe128He and Fe127VacHe : An uniaxial compression effect3
Addressing the impact of Lyman opacity in inference of divertor plasma conditions with 2D spectroscopic camera analysis of Balmer emission during detachment in JET L-mode plasmas3
Efficient capture of radioactive iodine by Ag-attached silica gel and its kinetics3
Utilization of boron particulate wall conditioning in the full tungsten environment of WEST3
Modeling input to the ITER glow discharge boronization system design3
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