Nuclear Materials and Energy

Article	Citations
Broadening of the power fall-off length in a high density, high confinement H-mode regime in ASDEX Upgrade	27
Determination of electron backscattering coefficient of beryllium by a high-precision Monte Carlo simulation	23
Plasma edge simulations including realistic wall geometry with SOLPS-ITER	21
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials	21
A study of the influence of plasma–molecule interactions on particle balance during detachment	20
Continuous observation of filaments from the confined region to the far scrape-off layer	20
Study on irradiation effects of refractory bcc high-entropy alloy	19
Divertor closure effects on the TCV boundary plasma	19
Preliminary analysis of alternative divertors for DEMO	19
An analysis of controlled detachment by seeding various impurity species in high performance scenarios on DIII-D and EAST	19
Impact of plasma-wall interaction and exhaust on the EU-DEMO design	18
Dust sampling in WEST and tritium retention in tokamak-relevant tungsten particles	18
First impurity powder injection experiments in LHD	17
Tungsten fuzz: Deposition effects and influence to fusion devices	16
Measurement of the 2D emission profiles of hydrogen and impurity ions in the TCV divertor	16
Origin and nature of the emissive sheath surrounding hot tungsten tokamak surfaces	16
Radiation resistance of single-mode optical fibres with view to in-reactor applications	16
Dynamic constitutive relationship of CuCrZr alloy based on Johnson-Cook model	16
Additive manufacturing of high density pure tungsten by electron beam melting	15
In-situ assessment of the emissivity of tungsten plasma facing components of the WEST tokamak	14
Thermal loads in gaps between ITER divertor monoblocks: First lessons learnt from WEST	13
SOLPS-ITER drift modelling of JET Ne and N-seeded H-modes	13
Infrared thermography in metallic environments of WEST and ASDEX Upgrade	13
Simulation of crack propagation behavior of nuclear graphite by using XFEM, VCCT and CZM methods	13
Overview of power exhaust experiments in the COMPASS divertor with liquid metals	13

Wall conditioning and ELM mitigation with boron nitride powder injection in KSTAR	13
Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER	12
Numerical benchmark of transient pressure-driven metallic melt flows	12
Evaluation of the hydrogen solubility and diffusivity in proton-conducting oxides by converting the PSL values of a tritium imaging plate	12
Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment	11
CF-LIBS quantification and depth profile analysis of Be coating mixed layers	11
Multiscale modelling for fusion and fission materials: The M4F project	11
Surface modified-gadolinium/boron/polyethylene composite with high shielding performance for neutron and gamma-ray	10
Perspective of analogy between heat loads and impurity production in L-mode discharges with ICRH in WEST	10
Arc behaviour on different materials in ASDEX Upgrade	10
Reassessing energy deposition for the ITER 5 MA vertical displacement event with an improved DINA model	10
Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys	10
3D modeling of boron transport in DIII-D L-mode wall conditioning experiments	10
Molecular dynamics simulation of displacement cascades in cubic silicon carbide	10
The role of edge fueling in determining the pedestal density in high neutral opacity Alcator C-Mod experiments	10
SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels	10
On the prediction and monitoring of tungsten prompt redeposition in tokamak divertors	10
Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments	10
Modeling of COMPASS tokamak divertor liquid metal experiments	10
The impact of surface morphology on the erosion of metallic surfaces – Modelling with the 3D Monte-Carlo code ERO2.0	9
Effects of a nitrogen seeded plasma on nanostructured tungsten films having fusion-relevant features	9
Generalization of the Heuristic Drift SOL model for finite collisionality and effect on flow shearing rate vs. interchange growth rate	9
Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels	9
Interaction between filaments and ICRF in the plasma edge	9
A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER	9
LIBS analysis of samples from the COMPASS vacuum chamber after liquid metal experiments – Li campaign	9
Study of liquid tin-lithium alloy interaction with structural materials of fusion reactor at high temperatures	9
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium	9
Comparison of DIVIMP and EDGE2D-EIRENE tungsten transport predictions in JET edge plasmas	8
Physics of the electric field in the scrape-off layer in ASDEX Upgrade L-mode discharges and comparison to experiments	8
Neutronics calculation of the conceptual TRISO duplex fuel rod design	8
Modeling of liquid lithium flow in porous plasma facing material	8
Establishing technical specifications for PbLi eutectic alloy analysis and its relevance in fusion applications	8
Liquid metal “divertorlets” concept for fusion reactors	8
Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET	8
Effect of elevated temperature on the magnetite and quartz concrete at different W/C ratios as nuclear shielding concretes	7
Development of DTT single null divertor scenario	7
Experimental verification of ion impact angle distribution at divertor surfaces using micro-engineered targets on DiMES at DIII-D	7
Depth distribution of irradiation-induced dislocation loops in an Fe-9Cr model alloy irradiated with Fe ions: The effect of ion energy	7
Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation	7
Investigation of hydrogen and deuterium impact on the release of tritium from two-phase lithium ceramics under reactor irradiation	7
Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation	7
Integrated modelling: Coupling of surface evolution and plasma-impurity transport	7
Impact of ion temperature anisotropy on 2D edge-plasma transport	7
Global distribution of tritium in JET with the ITER-like wall	7
13C tracer deposition in EAST D and He plasmas investigated by high-throughput deuteron nuclear reaction analysis mapping	7
Mechanical and microstructural response of the Al0.5CoCrFeNi high entropy alloy to Si and Ni ion irradiation	7
Hydrogen content in divertor baffle tiles in Wendelstein 7-X	7
Erosion and screening of tungsten during inter/intra-ELM periods in the JET-ILW divertor	7
Diffusion bonding effects on the adhesion of tungsten dust on tungsten surfaces	7

Estimation of 2D distributions of electron density and temperature in the JET divertor from tomographic reconstructions of deuterium Balmer line emission	7
Physical mechanisms and parameters for models of microstructure evolution under irradiation in Fe alloys – Part I: Pure Fe	7
Gamma radiation shielding property of continuous fiber reinforced epoxy matrix composite containing functional filler using Monte Carlo simulation	7
Experimental verification of X-point potential well formation in unfavorable magnetic field direction	7
Deuterium retention in tungsten and reduced activation steels after 3 MeV proton irradiation	7
Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices	7
Progress of tungsten spectral modeling for ITER edge plasma diagnostics based on tungsten spectroscopy in LHD	7
Corrosion behavior of diverse sputtered coatings for the helium cooled pebbles bed (HCPB) breeder concept	7
Experimental measurements and modeling of the deuterium release from tungsten co-deposited layers	7
Permeation and trapping of hydrogen in Eurofer97	6
Cross machine investigation of magnetic tokamak dust; structural and magnetic analysis	6
Scoping the characteristics and benefits of a connected double-null configuration for power exhaust in EU-DEMO	6
The transport of tungsten impurities induced by the intrinsic carbon during upper-single null discharge on EAST tokamak	6
High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam	6
Development of nano-oxide particles dispersed alumina scale formed on Zr-added FeCrAl ODS ferritic alloys	6
Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon content	6
Tungsten nitride as tritium permeation barrier	6
Parametric optimisation based on TDS experiments for rapid and efficient identification of hydrogen transport materials properties	6
Changes in morphology and field emission property of nano-tendril bundles after high temperature annealing	6
Radiation tolerance of alumina scale formed on FeCrAl ODS ferritic alloy	6
Analysis of the reactor experiments results on the study of gas evolution from two-phase Li2TiO3-Li4SiO4 lithium ceramics	6
Mechanical properties and stability of precipitates of an ODS steel after thermal cycling and aging	6
Modeling and experimental validation of a Wf	6
Result and discussion on the evolution of in-situ leading edge-induced melting on W divertor targets in EAST	6
Follow-up ultrasonic vibration assisted laser welding dissimilar metals for nuclear reactor pump can end sealing	6
Reproduction of collector probe deposition profiles using the far-SOL impurity transport code 3DLIM	6
Analytical expressions for thermophysical properties of solid and liquid beryllium relevant for fusion applications	6
Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design	6
Exposures of bulk W and nanostructured W coatings to medium flux D plasmas	6
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-6
Characterization on the melting failure of CuCrZr cooling tube of W/Cu monoblocks during plasma operations in EAST	6
Assessment of laser induced breakdown spectroscopy accuracy for determination of hydrogen accumulation in tungsten	6
Development of Gd-Si-O dispersed 316L stainless steel for improving neutron shielding performance	6
Design of a multi-configurations divertor for the DTT facility	6
Exposure of AlN and Al2O3 to low energy D and He plasmas	5
Neutron activation and radiation damage assessment for W-Ni-Fe tungsten heavy alloys with variable Ni content	5
Microstructural evolution and mechanical properties of friction stir welded 12Cr-ODS steel	5
Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten	5
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
Application of spatially hybrid fluid–kinetic neutral model on JET L-mode plasmas	5
Quantifying erosion and retention of silicon carbide due to D plasma irradiation in a high-flux linear plasma device	5
Microstructure stability, softening temperature and strengthening mechanism of pure copper, CuCrZr and Cu-Al2O3 up to 1000 ℃	5
Li mass loss and structure change due to long time heating in hydrogen atmosphere from Li2TiO3 with excess Li	5
Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions	5
Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection	5
An in-situ ToF-LEIS and AES study of near-surface modifications of the composition of EUROFER97 induced by thermal annealing	5
Fabrication and characterization of Cu reinforced with Y-enriched particles following a novel powder metallurgy route	5
Growth and characterization of W thin films with controlled Ne and Ar contents deposited by bipolar HiPIMS	5
Influence of thin tungsten oxide films on hydrogen isotope uptake and retention in tungsten – Evidence for permeation barrier effect	5
Rough-surface effect on sputtering of Cr bombarded by low-energy He plasma	5
Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options	5
Comprehensive modeling of hydrogen transport and accumulation in titanium and zirconium	5
Comparison of JET inner wall erosion in the first three ITER-like wall campaigns	5
Comparison experiment on the sputtering of EUROFER, RUSFER and CLAM steels by deuterium ions	5
Sustained radiative divertor in high-performance grassy-ELM regime with metal wall towards long-pulse operation in EAST	5
Kinetic model of the COMPASS tokamak SOL	5
Evaluation of bonding properties by flat indentation method for an EBW joint of RAFM steel for fusion application	5
Assessment of plasma power deposition on the ITER ICRH antennas	5
Lithium orthosilicate as nuclear fusion breeder material: Optimization of the drip casting production technology	5
Irradiation effects in tungsten—From surface effects to bulk mechanical properties	5
A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment	5
Modeling snowflake divertors in MAST-U tokamak using UEDGE code	5
Error analysis and cazlibration of Langmuir probes embedded in ITER-like tungsten divertor on EAST	5
Observations with fast visible cameras in high power Deuterium plasma experiments in the JET ITER-like wall tokamak	5
Uncertainty assessment for the displacement damage of a pressurized water reactor vessel	5
Atomistic simulation of the diffusion behavior in Al-Fe	5
The size dependence of microstructure and hardness on the MA powders for the MA-HIP processed Cu-Y2O3 dispersion-strengthened alloys	5
Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry	5
Boron transport simulation using the ERO2.0 code for real-time wall conditioning in the large helical device	4
Exploration of Sn70Li30 alloy as possible material for flowing liquid metal plasma facing components	4
Use of machine learning for a helium line intensity ratio method in Magnum-PSI	4
Angular dependence measurements of Magnum-PSI plasmas using MAST-U angled-tip Langmuir probes	4
Impact of the new TCV baffled divertor upgrade on pedestal structure and performance	4
Fuel recycling control in long pulse operation with full tungsten divertors in EAST tokamak	4
Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy	4
Preparation of hot-rolled potassium doped tungsten (KW) thick plate and performance of KW-Cu monoblock mock-ups under high heat flux testing	4
Corrosion behavior of ion-irradiated 12Cr2W2Mn F/M steel in liquid LBE	4
Investigation of the particle accumulation effects on the power exhaust of snowflake minus divertor on HL-2M tokamak by SOLPS-ITER	4
Evaluation of metal additive manufacturing for high-field modular-stellarator radial plates and conductors	4
Tungsten core accumulation study in EAST plasma with lower tungsten divertor by kinetic impurity transport model	4

Laser ablation of a solid target in liquid medium for beryllium nanoparticles synthesis	4
Study of detachment in future ASDEX Upgrade alternative divertor configurations by means of EMC3-EIRENE	4
Influences of displacement damage due to heavy ion irradiation on deuterium retention in CLF-1 steel	4
First analysis of in-situ melting on TZM tiles at high field side of the first wall in EAST	4
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
Deuterium retention in tungsten and tungsten alloys exposed to pure and impurities seeding deuterium plasma	4
Deuterium permeation through the low-activated V–4Cr–4Ti alloy under plasma irradiation	4
Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST	4
Comparison of a collisional-radiative fluid model of H2 in UEDGE to the kinetic neutral code EIRENE	4
The research on high-strength CICC jackets with YS > 1500 MPa at 4.2 K for future fusion applications	4
Dynamics and dependencies of the configuration-dependent 1–2 kHz fluctuation in W7-X	4
Lithium dilution in Li-Sn alloys	4
Exploring CuCrFeVTi system to produce high entropy alloys for high heat flux applications	4
Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak	4
Thermal-hydraulic modelling and analysis of ITER tungsten divertor monoblock	4
Experimental observations and modelling of radiation asymmetries during N2 seeding in LHD	4
Simulation of plasma transport in the linear plasma device MPS-LD by SOLPS-ITER	4
The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation	4
Toroidal flow measurements of impurity ions in QUEST ECH plasmas using multiple viewing chords emission spectroscopy	4
Impact of lithium wall conditioning and wave-frequency on high density lower hybrid current drive experiment on EAST	4
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys	4
Irradiation hardening behaviors of large-scale hot rolling potassium-doped tungsten alloy under synergistic irradiations of Fe11+ ion combined with deuterium and helium plasmas	4
Effects of F3+ ion implantation on the properties of W and W0.5(TaTiVCr)0.5 for depth marker-based plasma erosion analysis	4
Development of non-destructive testing (NDT) technique for HIPed interface by Compton scattering X-ray spectroscopy	4
Impacts of impurity flux on erosion and deposition of carbon/tungsten rough surfaces	4
Impurity control study of radiative tungsten divertor in EAST tokamak	4
Strongly temperature-dependent, anomalous secondary electron emission of liquid lithium surfaces exposed to a plasma	4
In-situ measurement of diffusion and surface segregation of W and Ta in bare and W-coated EUROFER97 during thermal annealing	4
High-accuracy compliance correction for nonlinear mechanical testing: Improving Small Punch Test characterization	4
Effect of annealing on microstructure and thermal conductivity of Li2TiO3 and Li4SiO4	4
Spectroscopic camera analysis of the roles of molecularly assisted reaction chains during detachment in JET L-mode plasmas	4
Fatigue properties of ferritic/martensitic steel after neutron irradiation and helium implantation	4
Investigation on the deformation mechanisms and size-dependent hardening effect of He bubbles in 84 dpa neutron irradiated Inconel X-750	4
Impact of seeded plasma impurities on D retention in RAFM steels	4
Observations on arcing on the metal plasma-facing components in EAST	3
Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature	3
Annihilation kinetics of irradiation defects in promising tritium breeding pebbles	3
High temperature recovery of radiation defects in tungsten and its effect on deuterium retention	3
Reaction–diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, I: Single cavity	3
Deuterium removal from beryllium co-deposits by simulated strike-point sweeping	3
Interstitial hydrogen atoms in W-nitride compounds promoting the formation of atomic vacancies in nuclear fusion reactors	3
Activation analysis for the reference low-activation vanadium alloy NIFS-HEAT-2	3
Wall conditioning effects and boron migration during boron powder injection in ASDEX Upgrade	3
Molecular dynamics simulation of defect production in Fe due to irradiation	3
Interlayer properties of tungsten fibre-reinforced composites and their determination by different methods	3
Investigation of the distribution of remaining tritium in divertor in LHD	3
Simulation of arc crater formation and evolution on plasma facing materials	3
Experiments and modelling on ASDEX Upgrade and WEST in support of tool development for tokamak reactor armour melting assessments	3
Heterogeneous microstructure and anisotropic mechanical properties of reduced activation ferritic/martensitic steel fabricated by wire arc additive manufacturing	3
Mechanical properties of several newly produced RAFM steels with Tungsten content in the range of 2 wt%	3
Deuterium retention in tungsten fiber-reinforced tungsten composites	3
Energy load on first wall components in high density, small ELM regimes in ASDEX Upgrade	3
Investigations on cold spray tungsten/tantalum coatings for plasma facing applications	3
Improved internal standard LIBS method used in CLF-1 exposure to liquid lithium	3
Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy	3
Thin films sputter-deposited from EUROFER97 in argon and deuterium atmosphere: Material properties and deuterium retention	3
Experimental investigation on corrosion of structural steels in molten Pb-Mg and LBE	3
Multi-code estimation of DTT edge transport parameters	3
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors	3
Currents structure in the scrape-off layer of a tokamak	3
Impact of negative triangularity on edge plasma transport and turbulence in TOKAM3X simulations	3
Blistering and deuterium retention in Nb-doped W exposed to low-energy deuterium plasma	3
Numerical modelling of the impact of leakage under divertor baffle in WEST	3
Characterization and evaluation of CuCrFeV(Ti, Ta, W) system for High Heat Flux applications	3
Validation of SOLPS-ITER simulations with kinetic, fluid, and hybrid neutral models for JET-ILW low-confinement mode plasmas	3
Impact of liquid metal surface on plasma-surface interaction in experiments with lithium and tin capillary porous systems	3
Radiation damage evolution in pure W and W-Cr-Hf alloy caused by 5 MeV Au ions in a broad range of dpa	3
First exploitation results of recently developed SXR GEM-based diagnostics at the WEST project	3
Decrease of blistering on Helium irradiated tungsten surface via transversal release of helium from the grooved surfaces	3
Parameter dependencies of the experimental nitrogen concentration required for detachment on ASDEX Upgrade and JET	3
Properties and thermal neutron areal transmittance of a B4C filled thermoplastic elastomer based rubber composite	3
Localized Nb clusters in U-Nb liquid alloys: An ab initio molecular dynamics study	3
Mechanical properties of self-ion irradiated pure tungsten using nano-indentation test and micro-tensile test	3
EMC3-EIRENE modelling of the toroidally asymmetric heat flux distribution with neon impurity injection on EAST	3
Failure investigation of nuclear grade POCO graphite target in high energy neutrino physics through numerical simulation	3
Indentation testing on 3 MeV proton irradiated tungsten	3
Role of zirconium in neodymium-dopants interactions within uranium-based metallic fuels	3
Effect of initial exposure temperature on the deuterium retention and surface blistering in tungsten	3
Divertor plasma opacity effects	3
Impact of vibrationally and electronically excited H2	3
A quantitative risk assessment methodology based on CCDF risk curve for accidental releases from fusion reactors	3
Elucidating the microstructure of tungsten composite materials produced by powder injection molding	3
Flux dependence of helium retention in clean W(1 1 0): Experimental evidence for He self-trapping	3
Characterisation of divertor detachment onset in JET-ILW hydrogen, deuterium, tritium and deuterium–tritium low-confinement mode plasmas	3
Three-dimensional structure of radiative cooling in impurity seeded plasmas in the Large Helical Device	3
Effect of temperature history on swelling behavior of V-Fe binary alloy irradiated in a fast reactor Joyo	3
Effect of HIP at 800 and 900 °C on microstructure and properties of extruded Be-Ti composites	3
Influence of Zr addition on the microstructure and mechanical properties of 9CrTi-ODS steels	3
First measurements of aluminum erosion by neutral particles on EAST tokamak	3
Structural study of W2B obtained via mechanical alloying of W, B4C, TiC and graphite before and after He ions irradiation	3
Investigation on tritium retention and surface properties on the first wall in the large helical Device	3
Nonlinear simulation of edge localized mode with pressure profile modified by pellet injection through a BOUT++ three-field MHD model	3
Hydrogen permeation and retention in deuterium plasma exposed 316L ITER steel	3
MHD stability constraints on divertor heat flux width in DIII-D	3
Control of deformation and annealing process to produce incoherent Σ3 boundaries in Hastelloy C-276 alloy	3