Journal of Nuclear Materials

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	132
Editorial Board	81
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	63
Editorial Board	62
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	61
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	58
The incorporation of xenon at point defects and bubbles in uranium mononitride	58
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	53
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	52
Effect of thermal oxidation on helium implanted pure iron	51
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	50
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	49
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	47
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	45
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	44
Effect of transmutation and active elements on the surface stability of silicon carbide	41
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	40
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	37
Raman spectroscopy of uranium nitride kernels	37
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	37
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	35
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	34
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]	34
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	32
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	32

Tungsten fiber-reinforced tungsten composites and their thermal stability	31
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	31
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	31
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	31
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	30
A deep learning interatomic potential model for the generation and evolution mechanisms of irradiation defects in yttrium hydride	30
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	29
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	29
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	29
Performance of high-Cr ODS steels under high-temperature neutron irradiation	29
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	29
Evidence of radiation induced segregation clustering in binary ferritic model alloys	29
Post-irradiation examination of AGR-3/4 TRISO fuel compacts using three-dimensional X-ray computed tomography	29
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	29
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	28
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	28
Development of GD-containing austenitic stainless steel	28
First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment	28
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	28
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	28
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	27
Sink effect on the microstructural evolution of defect clusters in Mo-Nb alloys during in-situ He ion irradiation	27
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	27
Microstructural evolution and radiation hardening of an alumina-forming duplex FeNiCrAl alloy under proton irradiation – Spatial dependence	27
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	27
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	27
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	27
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	26
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	26
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	26
The evolution of NiMnSi clusters in RPV steels under proton irradiation: The effect of Cu	26
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	25
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	25
Corrosion behavior of 316H stainless steel in molten LiF-UF4 and LiF-UF4-ZrF4 salts	25
Assessing the Role of Thermal Gradients in Abnormal Grain Growth of Tungsten Under Fusion-Relevant Conditions	25
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	25
Thermal diffusion behavior of ternary UMoX alloys with Al coating	24
Study on the preparation of highly efficient iodine capture activated carbon via dehydration of NH4H2PO4 combined with CO2 activation and its adsorption mechanism	24
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	24
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	24
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	24
Evaluation of neutron irradiation effects on mechanical properties of advanced EUROFER97 grades	23
Structural stability of β-phase uranium films at extreme temperatures	23
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	23
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	23
Enhanced Interfacial Stability and Helium Resistance via Tantalum Doping at Steel/W Interfaces for Nuclear Fusion Reactors	23
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	23
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy	23
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	23
Formation mechanisms of multilayered cobalt deposits on 304 stainless steel in primary cooling systems of pressurized water reactor nuclear power plants	22

Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	22
Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	22
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	22
Regulation mechanism of corrosion resistance in uranium-niobium-zirconium alloys: synergistic and concentration-dependent effects of alloying elements	22
Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool	22
Synergistic effects of hydrogen and helium on He bubble evolution in bcc-iron: A kinetic model	22
Deuterium behavior in tungsten following declining-temperature plasma exposures in two temperature ranges	22
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	21
Tensile properties of co-rolled Zr/U-10Mo fuel at ambient and elevated temperatures	21
Demonstration of industrially-fabricated plutonium disposition MOX	21
Flow-Accelerated Corrosion and Wall Thinning Mechanism of a Dissimilar Metal Welded Joint in the Secondary Loop Piping System of Pressurized Heavy Water Reactors	21
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	21
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	21
He clustering and role of vacancy in CuZr system	21
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	21
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	21
Editorial Board	21
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	21
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	21
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	21
Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	21
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	21
Finite temperature properties of uranium mononitride	20
Investigating the impact of yttria doping on radiation-induced crystallization in alumina	20
Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes	20
Threshold parameters of vacuum arcs with W-fuzz cathodes	20
Effect of microstructure on the delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tube	20
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	20
Achieving ultrahigh strength and high thermal stability of Cu-15 W composite by hierarchical structure with bimodal particle size distribution	20
The oxidation of uranium diboride in flowing air atmospheres	20
Development of a neural network potential for osmium enables irradiation damage simulations	19
Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors	19
Analytical W-H, H H and H He interatomic potentials for a W-H-He system	19
Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization	19
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	19
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	19
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds	19
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	19
Impact of PKA energy and spatial correlation of primary damage on irradiation microstructure evolution in iron: An object kinetic Monte Carlo simulation	19
Crud deposition behavior on zirconium alloy and Cr coated claddings in high temperature oxygenated water: The experimental and DFT studies	19
Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel	19
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	19
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	18
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	18
Radiation damage in ion-irradiated CeO2 and (Ce, Gd)O2 sinters: Effect of the Gd content	18
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	18
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	18
Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour	18
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions	18
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	18
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	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
Grain refinement and associated strengthening in laser additive repaired uranium	18
The diffusion of He in PuO2-x: Multi-scale simulation study	18
Leaching of B-Si-glass by water in the presence of bentonite	18
Assessment of EUROFER97, tungsten and CuCrZr alloy transmutation effects under IFMIF-DONES and DEMO conditions	18
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	18
Deformation strengthening of uranium and dilute uranium alloys	18
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	18
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	18
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	18
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	18
Mitigating the oxidation and carburization in austenitic stainless steels exposed to supercritical carbon dioxide by Al addition: the working mechanism	17
Numerical simulation study on the impact of helium bubbles on hydrogen isotope retention behavior in tungsten	17
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	17
Investigations of size effect and normalization models for tensile deformation of A508-III steel miniature specimens	17
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	17
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	17
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	17
Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	17
Simulations of grain growth in tungsten armor materials under ARC plasma edge operation conditions using an integrated plasma-edge/materials model	17
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	17
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	17
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	17
Hydrogen interaction with solid and liquid tin	17
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	17
Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	17
Influence of long term Sodium Exposure on the Corrosion and Tensile Properties of AISI Type 316LN stainless steel and modified 9Cr-1Mo steel	16
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe alloy	16
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	16

Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	16
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	16
Deuterium retention in the elements of plasma facing components for the DEMO first wall	16
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	16
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	16
Editorial Board	16
Thermal properties measurement of TRISO particle coatings from room temperature to 900 °C using laser-based thermoreflectance methods	16
Editorial Board	16
Density functional theory calculations of the mixing enthalpy of ternary uranium carbide compounds	16
Corrosion resistance and material optimization in supercritical water oxidation for radioactive waste treatment	16
Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	16
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	16
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	16
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	16
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	16
Morphology-governed rheology of RuO2 in borosilicate glass melts: Network formation and shear-thinning behavior	16
Influence of multi-ion concentrations on corrosion product deposition on zirconium alloy cladding in high-temperature water	16
Molecular-dynamics study of diffusional creep in uranium mononitride	16
Corrosion resistance of Ta-based TaCrWNbTi refractory high–entropy alloy coating in static lead–bismuth eutectic at 550 and 650℃ after 1000h	16
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	16
Significant amplification of irradiation dose effects by hydrogen-helium and the mechanism based on rate theory	16
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys	15
Editorial Board	15
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	15
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	15
Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	15
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	15
Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures	15
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	15
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	15
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	15
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	15
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	15
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	15
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	15
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	15
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	15
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	15
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	15
Atomistic mechanisms of hydrogenation corrosion resistance in representative uranium nitrides via ab initio molecular dynamics simulations	15
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	15
A first principles study of zirconium grain boundaries	15
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	15
Development of a coupling facility for high-energy proton irradiation and high-temperature high-pressure water corrosion	15
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	15
Characterization of the role of heat-treatment on the microstructure and texture evolution of Zr-2.5 %Nb Alloy	15
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	15
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	15
X-site element dependence of radiation resistance in Zr2SeC and Zr2SeP covalent MAX phases	15
Impact of metallic Mo nanoparticles on the dissolution kinetics of UO2 in nitric acid under representative PUREX process conditions	14
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	14
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	14
UO2 solubility and chemical interactions in molten LiCl-Li2O	14
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt	14
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys	14
How brittle is 'too brittle'?: Comparative mechanical assessment of silicon carbide and post-quench steam-oxidized zirconium alloy cladding	14
Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings	14
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	14
Heat-treated additively manufactured and wrought 316L steels display a comparable response to ion irradiation	14
About the role of iron on the alteration of simplified nuclear glasses in deaerated solutions at 50°C	14
Phonon modal analysis of thermal transport in ThO2 with point defects using equilibrium molecular dynamics	14
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	14
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	14
Oxidation and degradation of Cr-coated Zr-based alloy up to 1500°C: Effect of Cr thickness	14
Effect of radial hydrides on fracture behavior of Zr-2.5Nb pressure tube material	14
Enabling BWR fuel rod analysis in the BISON fuel performance code	14
Solid-state welding for dissimilar zirconium alloy under joule heating effect: Material flowing behavior, characteristics, evolution and formation of interface	14
Molecular dynamics study of primary damage in the near-surface region in nickel	14
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	14
Editorial Board	14
Editorial Board	14
Effect of free surfaces on localized plastic deformation in single-crystal nickel containing helium bubbles and radiation-induced self-interstitial atom clusters	14
Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings	14
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	14
Role of magnesium ions in modifying oxide growth rate on Zircaloy under breakaway corrosion regimes	14
Variations in the contents of crystalline phases in the Chornobyl lava specimen	14
Post irradiated microstructure and mechanical properties of pure V	14
Contributions of Ni-content and irradiation temperature to the kinetic of solute cluster formation and consequences on the hardening of VVER materials	14
Insights into stress corrosion crack growth of 316NG heat-affected zone in simulated PWR primary water	14
Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys	14
Molecular dynamics simulation of bubble growth under surface of tungsten under helium irradiation	14
Accelerated prediction of lattice thermal conductivity of Zirconium and its alloys: A machine learning potential method	14
Editorial Board	14
Effects of surface treatments and temperature on the oxidation behavior of 308L stainless steel cladding in hydrogenated high-temperature water	13
Fabrication and thermal conductivity of UN-UB2 composites fabricated by spark plasma sintering	13
Multiscale study of helium diffusion in Ni-Cr alloys: Short-range trapping versus long-range channeling	13
Deterioration of irradiation resistance of ODS-F/M steel under high concentration of helium	13
Microstructural evolution of ion-irradiated commercially pure titanium	13
Role of chemical disorder on radiation-induced defect production and damage evolution in NiFeCoCr	13
Calculation of neutron-induced radiation damage to gold and lutetium-aluminium microstructures using MCNP6.2	13
Modelling of physical sputtering properties during tungsten fuzz growth under various impact energies on NAGDIS-II	13
Effects of thermal aging on the stress corrosion cracking behavior of cast stainless steel with different δ-ferrite levels in high temperature water environment	13
Irradiation-induced chemical disordering in ceramics: The case of SiC	13
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	13
Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics	13