Journal of Nuclear Materials

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	133
Editorial Board	86
Editorial Board	72
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	67
The incorporation of xenon at point defects and bubbles in uranium mononitride	65
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	62
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	56
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	55
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	54
Raman spectroscopy of uranium nitride kernels	49
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	49
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	47
Corrigendum to “Experimental assessment of thermodynamic stability and nucleation of NiO in liquid lead-bismuth eutectic for MYRRHA” [Journal of Nuclear Materials 603 (2025) 155404]	47
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	45
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	41
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	41
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	41
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	40
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	39
A deep learning interatomic potential model for the generation and evolution mechanisms of irradiation defects in yttrium hydride	37
Performance of high-Cr ODS steels under high-temperature neutron irradiation	37
Post-irradiation examination of AGR-3/4 TRISO fuel compacts using three-dimensional X-ray computed tomography	35
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	34
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	34
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	33

Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	32
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	32
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	31
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	31
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	31
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	31
First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment	31
Corrosion behavior of 316H stainless steel in molten LiF-UF4 and LiF-UF4-ZrF4 salts	31
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	31
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	30
Microstructural evolution and radiation hardening of an alumina-forming duplex FeNiCrAl alloy under proton irradiation – Spatial dependence	30
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	30
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	30
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	30
Evidence of radiation induced segregation clustering in binary ferritic model alloys	29
Development of GD-containing austenitic stainless steel	29
Effect of thermal oxidation on helium implanted pure iron	29
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	29
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	29
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	29
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	29
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	29
Thermal diffusion behavior of ternary UMoX alloys with Al coating	28
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	28
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	28
Study on the preparation of highly efficient iodine capture activated carbon via dehydration of NH4H2PO4 combined with CO2 activation and its adsorption mechanism	27
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	27
The evolution of NiMnSi clusters in RPV steels under proton irradiation: The effect of Cu	27
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	27
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	26
Zirconia layer stoichiometry during steam oxidation of M5FRAMATOME cladding alloy under LOCA conditions	26
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	26
Assessing the role of thermal gradients in abnormal grain growth of tungsten under fusion-relevant conditions	26
Sink effect on the microstructural evolution of defect clusters in Mo-Nb alloys during in-situ He ion irradiation	26
Defect formation and transmutation behaviors in irradiated tungsten under thermal-neutron shielded and mixed spectrum conditions	26
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	25
Tungsten fiber-reinforced tungsten composites and their thermal stability	25
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	25
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	25
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	25
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	25
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	25
Structural stability of β-phase uranium films at extreme temperatures	24
Systematic experimental and model-based evaluation of the synergistic effects of alloy composition and damage rate on the formation of Cr-rich precipitates in Fe–Cr–Al alloys under ion irradiation	24
Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	24
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy	24
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	24
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	24
Effect of transmutation and active elements on the surface stability of silicon carbide	24
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	24

Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	23
Demonstration of industrially-fabricated plutonium disposition MOX	23
Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool	23
He clustering and role of vacancy in CuZr system	23
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	23
Deuterium behavior in tungsten following declining-temperature plasma exposures in two temperature ranges	23
Tensile properties of co-rolled Zr/U-10Mo fuel at ambient and elevated temperatures	23
Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	23
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	22
The effect of static stresses on the acceleration of the decomposition processes in the ferritic-martensitic steels in conditions of neutron irradiation to a dose of 85 dpa	22
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	22
Editorial Board	22
Development of a neural network potential for osmium enables irradiation damage simulations	22
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	22
Investigating the impact of yttria doping on radiation-induced crystallization in alumina	22
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	22
Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors	22
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	21
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	21
Grain refinement and associated strengthening in laser additive repaired uranium	21
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	21
Deformation strengthening of uranium and dilute uranium alloys	21
Synergistic effects of hydrogen and helium on He bubble evolution in bcc-iron: A kinetic model	21
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	21
Post-LOCA ductility assessment of Zr-Nb Alloy from 1100°C to 1300°C to explore variable peak cladding temperature and equivalent cladding reacted safety criteria	21
Impact of PKA energy and spatial correlation of primary damage on irradiation microstructure evolution in iron: An object kinetic Monte Carlo simulation	21
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	20
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	20
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	20
Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel	20
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	20
Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour	20
Finite temperature properties of uranium mononitride	20
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	20
Crud deposition behavior on zirconium alloy and Cr coated claddings in high temperature oxygenated water: The experimental and DFT studies	20
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	20
Threshold parameters of vacuum arcs with W-fuzz cathodes	20
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds	20
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	19
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	19
Assessment of EUROFER97, tungsten and CuCrZr alloy transmutation effects under IFMIF-DONES and DEMO conditions	19
Leaching of B-Si-glass by water in the presence of bentonite	19
Structural, electronic, transport and thermodynamic properties of layered rare-earth nickelates: a first-principles study relevant to nuclear materials	19
The effect of annealing treatment on plasma induced surface blistering and deuterium retention in tungsten	19
Achieving ultrahigh strength and high thermal stability of Cu-15 W composite by hierarchical structure with bimodal particle size distribution	19
Regulation mechanism of corrosion resistance in uranium-niobium-zirconium alloys: synergistic and concentration-dependent effects of alloying elements	19
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	19
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	19
UO2-Mo-Nb composite nuclear fuel thermal conductivity and thermal stress coupling analysis through the machine learning and NSGA-II algorithm	19
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	19
The oxidation of uranium diboride in flowing air atmospheres	19
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	19
Analytical W-H, H H and H He interatomic potentials for a W-H-He system	19
Flow-Accelerated Corrosion and Wall Thinning Mechanism of a Dissimilar Metal Welded Joint in the Secondary Loop Piping System of Pressurized Heavy Water Reactors	19
Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization	18
Formation mechanisms of multilayered cobalt deposits on 304 stainless steel in primary cooling systems of pressurized water reactor nuclear power plants	18
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	18
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	18
Investigations of size effect and normalization models for tensile deformation of A508-III steel miniature specimens	18
Thermodynamic properties of uranium-zirconium carbide solid solutions with oxygen	18
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	18
NOx Mediated Formation of ε – UO3 During Thermal Decomposition of Uranyl Nitrate Hexahydrate under Static Air Conditions	18
High temperature deformation behavior of a novel Zr-Nb-Sn-Fe alloy: Constitutive analysis and microstructural development	18
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	18
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	18
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	18
Numerical simulation study on the impact of helium bubbles on hydrogen isotope retention behavior in tungsten	18
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	18
Effect of microstructure on the delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tube	18
The stability and behavior of Cr-rich α' precipitates under cascade damage in Fe-15Cr-8Al ternary alloys: An atomic-scale simulation study	18
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	18
Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	18
Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	18
Significant amplification of irradiation dose effects by hydrogen-helium and the mechanism based on rate theory	17
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	17
Editorial Board	17
In-pile heat conduction model of the dispersion nuclear fuel plate with particle agglomeration. Part II: Predicting the effective thermal conductivity under the in-pile thermal transfer pattern based	17
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	17
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	17
Corrosion resistance and material optimization in supercritical water oxidation for radioactive waste treatment	17

Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	17
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	17
Editorial Board	17
Morphology-governed rheology of RuO2 in borosilicate glass melts: Network formation and shear-thinning behavior	17
Corrosion resistance of Ta-based TaCrWNbTi refractory high–entropy alloy coating in static lead–bismuth eutectic at 550 and 650℃ after 1000h	17
Editorial Board	17
Mitigating the oxidation and carburization in austenitic stainless steels exposed to supercritical carbon dioxide by Al addition: the working mechanism	17
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe alloy	17
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	17
Density functional theory calculations of the mixing enthalpy of ternary uranium carbide compounds	17
Deuterium retention in the elements of plasma facing components for the DEMO first wall	17
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	16
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	16
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	16
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	16
Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures	16
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	16
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	16
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	16
Normal spectral emissivity, specific heat capacity, and thermal conductivity of type 316 austenitic stainless steel containing up to 10 mass% B4C in a liquid state	16
Atomistic mechanisms of hydrogenation corrosion resistance in representative uranium nitrides via ab initio molecular dynamics simulations	16
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	16
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	16
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	16
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	16
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	16
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	16
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	16
Development of a coupling facility for high-energy proton irradiation and high-temperature high-pressure water corrosion	16
Modern measurement of local radial thermal conductivity of irradiated he-bonded U-10 wt. % Zr annular fuel: A cross-correlative study with electron probe microanalysis techniques	16
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	16
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	16
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys	16
Characterization of the role of heat-treatment on the microstructure and texture evolution of Zr-2.5 %Nb Alloy	16
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	16
Molecular-dynamics study of diffusional creep in uranium mononitride	16
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	16
Simulations of grain growth in tungsten armor materials under ARC plasma edge operation conditions using an integrated plasma-edge/materials model	16
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	15
Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	15
Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	15
X-site element dependence of radiation resistance in Zr2SeC and Zr2SeP covalent MAX phases	15
Irradiation-induced phase reversion of discontinuous precipitation in U10Mo alloy	15
Accelerated prediction of lattice thermal conductivity of Zirconium and its alloys: A machine learning potential method	15
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	15
Editorial Board	15
Hydrogen interaction with solid and liquid tin	15
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	15
Estimating the residual stresses in Zr-2.5%Nb pressure tubes using hydride reorientation phenomenon	15
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	15
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	15
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	15
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	15
Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings	15
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	15
Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings	15
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	15
Influence of multi-ion concentrations on corrosion product deposition on zirconium alloy cladding in high-temperature water	15
Effects of Composition and Oxidation States on the Structures of Chromium-Containing Sodium Silicate Glasses: Molecular Dynamics Simulations using Machine Learning Interatomic Potentials	15
Impedance spectroscopy investigation of phase separation in SiO₂-B2O3-Na2O-MoO₃ simplified nuclear melts	15
A first principles study of zirconium grain boundaries	15
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	15
Influence of long term Sodium Exposure on the Corrosion and Tensile Properties of AISI Type 316LN stainless steel and modified 9Cr-1Mo steel	15
Contributions of Ni-content and irradiation temperature to the kinetic of solute cluster formation and consequences on the hardening of VVER materials	15
Variations in the contents of crystalline phases in the Chornobyl lava specimen	15
Editorial Board	15
Phonon modal analysis of thermal transport in ThO2 with point defects using equilibrium molecular dynamics	15
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	15
Simulation of defect build-up in tungsten during low energy irradiation	14
Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen	14
Micromechanical response of SiC-OPyC layers in TRISO fuel particles	14
Helium interaction with solutes and impurities in neutron-irradiated nanostructured ferritic alloys: A first principles study	14
Enabling BWR fuel rod analysis in the BISON fuel performance code	14
Fabrication and thermal conductivity of UN-UB2 composites fabricated by spark plasma sintering	14
On the performance of metallic coating barriers in U-Mo/Al fuels: A quantitative evaluation of Al/X/U-Mo trilayer structures (X = Mo, Zr, or W) under heavy ion irradiation	14
Study of fusion boundary microstructure and local mismatch of SA508/alloy 52 dissimilar metal weld with buttering	14
Defect annealing in heavy-ion irradiated tungsten: Long-time thermal evolution of saturated displacement damage at different temperatures	14
How brittle is 'too brittle'?: Comparative mechanical assessment of silicon carbide and post-quench steam-oxidized zirconium alloy cladding	14
Effects of thermal aging on the stress corrosion cracking behavior of cast stainless steel with different δ-ferrite levels in high temperature water environment	14
Deterioration of irradiation resistance of ODS-F/M steel under high concentration of helium	14
On the influence of specimen size and geometry on the fracture toughness of tungsten heavy metal alloys	14
Corrosion study of zirconium alloys via molecular dynamics simulations: I. oxygen migration in zirconium oxides under low-dose irradiation induced displacement damage	14
Molecular dynamics simulation of bubble growth under surface of tungsten under helium irradiation	14
Calculation of neutron-induced radiation damage to gold and lutetium-aluminium microstructures using MCNP6.2	14
Environmentally-assisted cracking of electropolished 316L stainless steel in molten FLiNaK salt	14
Improving the corrosion resistance of structural materials in liquid lead-bismuth eutectic alloys: Combined machine learning and molecular dynamics	14
Lead-bismuth eutectic corrosion behavior of NbMoVCr refractory multi-principal element alloys coating synthesized by magnetron sputtering	14
Solid-state welding for dissimilar zirconium alloy under joule heating effect: Material flowing behavior, characteristics, evolution and formation of interface	14
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys	14
Microstructural evolution of ion-irradiated commercially pure titanium	14
The Effect of Proton Irradiation on In-situ Corrosion Behavior of Zr-Sn-Nb Zirconium Alloy under Simulated PWR Water Condition	14
Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation	14
Effect of lithium on the atmospheric corrosion characteristics of TZM as the first-wall material in EAST	14
Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles	14
Alteration of fresh MIMAS MOX and (U,Ce)O2 analogous materials in simplified cementitious water	14