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 2020-05-01 to 2024-05-01.)
ArticleCitations
Broadening of the power fall-off length in a high density, high confinement H-mode regime in ASDEX Upgrade27
Determination of electron backscattering coefficient of beryllium by a high-precision Monte Carlo simulation24
Divertor closure effects on the TCV boundary plasma22
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials22
Plasma edge simulations including realistic wall geometry with SOLPS-ITER21
Impact of plasma-wall interaction and exhaust on the EU-DEMO design21
A study of the influence of plasma–molecule interactions on particle balance during detachment20
Continuous observation of filaments from the confined region to the far scrape-off layer20
An analysis of controlled detachment by seeding various impurity species in high performance scenarios on DIII-D and EAST20
Preliminary analysis of alternative divertors for DEMO19
Study on irradiation effects of refractory bcc high-entropy alloy19
Dust sampling in WEST and tritium retention in tokamak-relevant tungsten particles18
First impurity powder injection experiments in LHD17
Additive manufacturing of high density pure tungsten by electron beam melting16
Dynamic constitutive relationship of CuCrZr alloy based on Johnson-Cook model16
Tungsten fuzz: Deposition effects and influence to fusion devices16
Measurement of the 2D emission profiles of hydrogen and impurity ions in the TCV divertor16
Origin and nature of the emissive sheath surrounding hot tungsten tokamak surfaces16
Radiation resistance of single-mode optical fibres with view to in-reactor applications16
Overview of power exhaust experiments in the COMPASS divertor with liquid metals14
In-situ assessment of the emissivity of tungsten plasma facing components of the WEST tokamak14
Thermal loads in gaps between ITER divertor monoblocks: First lessons learnt from WEST13
SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes13
Simulation of crack propagation behavior of nuclear graphite by using XFEM, VCCT and CZM methods13
Infrared thermography in metallic environments of WEST and ASDEX Upgrade13
Wall conditioning and ELM mitigation with boron nitride powder injection in KSTAR13
Evaluation of the hydrogen solubility and diffusivity in proton-conducting oxides by converting the PSL values of a tritium imaging plate12
Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER12
Numerical benchmark of transient pressure-driven metallic melt flows12
Multiscale modelling for fusion and fission materials: The M4F project11
SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels11
On the prediction and monitoring of tungsten prompt redeposition in tokamak divertors11
Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment11
CF-LIBS quantification and depth profile analysis of Be coating mixed layers11
Surface modified-gadolinium/boron/polyethylene composite with high shielding performance for neutron and gamma-ray11
Liquid metal “divertorlets” concept for fusion reactors10
Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments10
Modeling of COMPASS tokamak divertor liquid metal experiments10
3D modeling of boron transport in DIII-D L-mode wall conditioning experiments10
Arc behaviour on different materials in ASDEX Upgrade10
Reassessing energy deposition for the ITER 5 MA vertical displacement event with an improved DINA model10
Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys10
Generalization of the Heuristic Drift SOL model for finite collisionality and effect on flow shearing rate vs. interchange growth rate10
Molecular dynamics simulation of displacement cascades in cubic silicon carbide10
The role of edge fueling in determining the pedestal density in high neutral opacity Alcator C-Mod experiments10
Perspective of analogy between heat loads and impurity production in L-mode discharges with ICRH in WEST10
Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices9
Interaction between filaments and ICRF in the plasma edge9
A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER9
LIBS analysis of samples from the COMPASS vacuum chamber after liquid metal experiments – Li campaign9
Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels9
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium9
The impact of surface morphology on the erosion of metallic surfaces – Modelling with the 3D Monte-Carlo code ERO2.09
Effects of a nitrogen seeded plasma on nanostructured tungsten films having fusion-relevant features9
Study of liquid tin-lithium alloy interaction with structural materials of fusion reactor at high temperatures9
Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications8
Comparison of DIVIMP and EDGE2D-EIRENE tungsten transport predictions in JET edge plasmas8
Modeling of liquid lithium flow in porous plasma facing material8
Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation8
Neutronics calculation of the conceptual TRISO duplex fuel rod design8
Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET8
Erosion and screening of tungsten during inter/intra-ELM periods in the JET-ILW divertor8
Physics of the electric field in the scrape-off layer in ASDEX Upgrade L-mode discharges and comparison to experiments8
Corrosion behavior of diverse sputtered coatings for the helium cooled pebbles bed (HCPB) breeder concept7
Experimental measurements and modeling of the deuterium release from tungsten co-deposited layers7
Effect of elevated temperature on the magnetite and quartz concrete at different W/C ratios as nuclear shielding concretes7
Development of DTT single null divertor scenario7
Experimental verification of X-point potential well formation in unfavorable magnetic field direction7
Deuterium retention in tungsten and reduced activation steels after 3 MeV proton irradiation7
Modeling and experimental validation of a Wf7
Progress of tungsten spectral modeling for ITER edge plasma diagnostics based on tungsten spectroscopy in LHD7
Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation7
Integrated modelling: Coupling of surface evolution and plasma-impurity transport7
Impact of ion temperature anisotropy on 2D edge-plasma transport7
Growth and characterization of W thin films with controlled Ne and Ar contents deposited by bipolar HiPIMS7
Experimental verification of ion impact angle distribution at divertor surfaces using micro-engineered targets on DiMES at DIII-D7
Depth distribution of irradiation-induced dislocation loops in an Fe-9Cr model alloy irradiated with Fe ions: The effect of ion energy7
Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation7
Diffusion bonding effects on the adhesion of tungsten dust on tungsten surfaces7
Estimation of 2D distributions of electron density and temperature in the JET divertor from tomographic reconstructions of deuterium Balmer line emission7
Physical mechanisms and parameters for models of microstructure evolution under irradiation in Fe alloys – Part I: Pure Fe7
Gamma radiation shielding property of continuous fiber reinforced epoxy matrix composite containing functional filler using Monte Carlo simulation7
Global distribution of tritium in JET with the ITER-like wall7
13C tracer deposition in EAST D and He plasmas investigated by high-throughput deuteron nuclear reaction analysis mapping7
Mechanical and microstructural response of the Al0.5CoCrFeNi high entropy alloy to Si and Ni ion irradiation7
Hydrogen content in divertor baffle tiles in Wendelstein 7-X7
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-7
Follow-up ultrasonic vibration assisted laser welding dissimilar metals for nuclear reactor pump can end sealing6
Design of a multi-configurations divertor for the DTT facility6
Permeation and trapping of hydrogen in Eurofer976
Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten6
Scoping the characteristics and benefits of a connected double-null configuration for power exhaust in EU-DEMO6
Analysis of the reactor experiments results on the study of gas evolution from two-phase Li2TiO3-Li4SiO4 lithium ceramics6
Characterization on the melting failure of CuCrZr cooling tube of W/Cu monoblocks during plasma operations in EAST6
Result and discussion on the evolution of in-situ leading edge-induced melting on W divertor targets in EAST6
Atomistic simulation of the diffusion behavior in Al-Fe6
Uncertainty assessment for the displacement damage of a pressurized water reactor vessel6
Parametric optimisation based on TDS experiments for rapid and efficient identification of hydrogen transport materials properties6
Changes in morphology and field emission property of nano-tendril bundles after high temperature annealing6
Cross machine investigation of magnetic tokamak dust; structural and magnetic analysis6
Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy6
Exposures of bulk W and nanostructured W coatings to medium flux D plasmas6
The transport of tungsten impurities induced by the intrinsic carbon during upper-single null discharge on EAST tokamak6
Observations with fast visible cameras in high power Deuterium plasma experiments in the JET ITER-like wall tokamak6
Mechanical properties and stability of precipitates of an ODS steel after thermal cycling and aging6
Development of Gd-Si-O dispersed 316L stainless steel for improving neutron shielding performance6
Assessment of laser induced breakdown spectroscopy accuracy for determination of hydrogen accumulation in tungsten6
Microstructure stability, softening temperature and strengthening mechanism of pure copper, CuCrZr and Cu-Al2O3 up to 1000 ℃6
Reproduction of collector probe deposition profiles using the far-SOL impurity transport code 3DLIM6
Analytical expressions for thermophysical properties of solid and liquid beryllium relevant for fusion applications6
Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design6
High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam6
Development of nano-oxide particles dispersed alumina scale formed on Zr-added FeCrAl ODS ferritic alloys6
Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content6
The size dependence of microstructure and hardness on the MA powders for the MA-HIP processed Cu-Y2O3 dispersion-strengthened alloys6
Tungsten nitride as tritium permeation barrier6
Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry5
Evaluation of bonding properties by flat indentation method for an EBW joint of RAFM steel for fusion application5
Assessment of plasma power deposition on the ITER ICRH antennas5
Decrease of blistering on Helium irradiated tungsten surface via transversal release of helium from the grooved surfaces5
Irradiation effects in tungsten—From surface effects to bulk mechanical properties5
A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment5
Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options5
Dynamics and dependencies of the configuration-dependent 1–2 kHz fluctuation in W7-X5
Comparison of JET inner wall erosion in the first three ITER-like wall campaigns5
High-accuracy compliance correction for nonlinear mechanical testing: Improving Small Punch Test characterization5
Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions5
Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection5
Exposure of AlN and Al2O3 to low energy D and He plasmas5
Neutron activation and radiation damage assessment for W-Ni-Fe tungsten heavy alloys with variable Ni content5
Lithium orthosilicate as nuclear fusion breeder material: Optimization of the drip casting production technology5
Rough-surface effect on sputtering of Cr bombarded by low-energy He plasma5
Influence of thin tungsten oxide films on hydrogen isotope uptake and retention in tungsten – Evidence for permeation barrier effect5
Error analysis and cazlibration of Langmuir probes embedded in ITER-like tungsten divertor on EAST5
Quantifying erosion and retention of silicon carbide due to D plasma irradiation in a high-flux linear plasma device5
Application of spatially hybrid fluid–kinetic neutral model on JET L-mode plasmas5
Li mass loss and structure change due to long time heating in hydrogen atmosphere from Li2TiO3 with excess Li5
Kinetic model of the COMPASS tokamak SOL5
Divertor plasma opacity effects5
An in-situ ToF-LEIS and AES study of near-surface modifications of the composition of EUROFER97 induced by thermal annealing5
Fabrication and characterization of Cu reinforced with Y-enriched particles following a novel powder metallurgy route5
Microstructural evolution and mechanical properties of friction stir welded 12Cr-ODS steel5
Exploration of Sn70Li30 alloy as possible material for flowing liquid metal plasma facing components5
Modeling snowflake divertors in MAST-U tokamak using UEDGE code5
Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)5
Deuterium permeation through the low-activated V–4Cr–4Ti alloy under plasma irradiation5
Comprehensive modeling of hydrogen transport and accumulation in titanium and zirconium5
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions5
Sustained radiative divertor in high-performance grassy-ELM regime with metal wall towards long-pulse operation in EAST5
Characterisation of divertor detachment onset in JET-ILW hydrogen, deuterium, tritium and deuterium–tritium low-confinement mode plasmas4
Impact of seeded plasma impurities on D retention in RAFM steels4
First exploitation results of recently developed SXR GEM-based diagnostics at the WEST project4
Boron transport simulation using the ERO2.0 code for real-time wall conditioning in the large helical device4
Strongly temperature-dependent, anomalous secondary electron emission of liquid lithium surfaces exposed to a plasma4
Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy4
Lithium dilution in Li-Sn alloys4
Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST4
Impacts of impurity flux on erosion and deposition of carbon/tungsten rough surfaces4
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications4
Failure investigation of nuclear grade POCO graphite target in high energy neutrino physics through numerical simulation4
Lithium splashing from flowing liquid lithium limiter and its effect on high confinement plasma performance in EAST tokamak4
Irradiation hardening behaviors of large-scale hot rolling potassium-doped tungsten alloy under synergistic irradiations of Fe11+ ion combined with deuterium and helium plasmas4
Experimental observations and modelling of radiation asymmetries during N2 seeding in LHD4
Effect of initial exposure temperature on the deuterium retention and surface blistering in tungsten4
Fatigue properties of ferritic/martensitic steel after neutron irradiation and helium implantation4
Exploring CuCrFeVTi system to produce high entropy alloys for high heat flux applications4
Wall conditioning effects and boron migration during boron powder injection in ASDEX Upgrade4
In-situ measurement of diffusion and surface segregation of W and Ta in bare and W-coated EUROFER97 during thermal annealing4
Impact of lithium wall conditioning and wave-frequency on high density lower hybrid current drive experiment on EAST4
Evaluation of metal additive manufacturing for high-field modular-stellarator radial plates and conductors4
The regularities of creep deformation and failure of the VVER’s pressure vessel steel 15Kh2NMFA-A in air and argon at temperature range 500–900 °C”4
Parameter dependencies of the experimental nitrogen concentration required for detachment on ASDEX Upgrade and JET4
Deuterium retention in tungsten and tungsten alloys exposed to pure and impurities seeding deuterium plasma4
Investigation of the particle accumulation effects on the power exhaust of snowflake minus divertor on HL-2M tokamak by SOLPS-ITER4
The research on high-strength CICC jackets with YS > 1500 MPa at 4.2 K for future fusion applications4
Hydrogen permeation and retention in deuterium plasma exposed 316L ITER steel4
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys4
Preparation of hot-rolled potassium doped tungsten (KW) thick plate and performance of KW-Cu monoblock mock-ups under high heat flux testing4
Tungsten core accumulation study in EAST plasma with lower tungsten divertor by kinetic impurity transport model4
Effect of annealing on microstructure and thermal conductivity of Li2TiO3 and Li4SiO44
Selection of radiation tolerant commercial greases for high-radiation areas at CERN: Methodology and applications4
Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis4
Angular dependence measurements of Magnum-PSI plasmas using MAST-U angled-tip Langmuir probes4
Spectroscopic camera analysis of the roles of molecularly assisted reaction chains during detachment in JET L-mode plasmas4
Development of non-destructive testing (NDT) technique for HIPed interface by Compton scattering X-ray spectroscopy4
Influences of displacement damage due to heavy ion irradiation on deuterium retention in CLF-1 steel4
Fuel recycling control in long pulse operation with full tungsten divertors in EAST tokamak4
First analysis of in-situ melting on TZM tiles at high field side of the first wall in EAST4
Comparison of a collisional-radiative fluid model of H2 in UEDGE to the kinetic neutral code EIRENE4
Toroidal flow measurements of impurity ions in QUEST ECH plasmas using multiple viewing chords emission spectroscopy4
Simulation of arc crater formation and evolution on plasma facing materials4
Influence of Zr addition on the microstructure and mechanical properties of 9CrTi-ODS steels4
Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy4
Effects of F3+ ion implantation on the properties of W and W0.5(TaTiVCr)0.5 for depth marker-based plasma erosion analysis4
Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak4
Use of machine learning for a helium line intensity ratio method in Magnum-PSI4
A quantitative risk assessment methodology based on CCDF risk curve for accidental releases from fusion reactors4
Impact of the new TCV baffled divertor upgrade on pedestal structure and performance4
Thermal-hydraulic modelling and analysis of ITER tungsten divertor monoblock4
Microstructural, mechanical properties and high temperature oxidation of Cr, Al-coated Zr-4 alloy4
Investigation on effects of tritium release behavior in Li4SiO4 pebbles4
Study of detachment in future ASDEX Upgrade alternative divertor configurations by means of EMC3-EIRENE4
Impact of negative triangularity on edge plasma transport and turbulence in TOKAM3X simulations4
Simulation of plasma transport in the linear plasma device MPS-LD by SOLPS-ITER4
Corrosion behavior of ion-irradiated 12Cr2W2Mn F/M steel in liquid LBE4
The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation4
Impurity control study of radiative tungsten divertor in EAST tokamak4
Investigation on the deformation mechanisms and size-dependent hardening effect of He bubbles in 84 dpa neutron irradiated Inconel X-7504
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