Journal of Nuclear Materials

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	224
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	105
Editorial Board	74
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	70
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]	67
Effect of thermal oxidation on helium implanted pure iron	64
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	62
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	60
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	55
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	50
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	50
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	46
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	45
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	43
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	41
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	40
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	39
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	39
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	38
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	38
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	38
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	37
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	36
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	36
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	36

The incorporation of xenon at point defects and bubbles in uranium mononitride	34
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements	34
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	34
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	33
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	33
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	32
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	32
Editorial Board	32
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	32
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	31
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	31
Annealing of the Raman defect peaks in He-implanted UO2	30
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	30
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	30
Raman spectroscopy of uranium nitride kernels	30
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	30
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	30
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	30
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	29
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	29
A molecular dynamics study of a cascade induced irradiation creep mechanism in pure copper	29
Thermal diffusion behavior of ternary UMoX alloys with Al coating	29
Effect of transmutation and active elements on the surface stability of silicon carbide	29
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	28
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	28
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	27
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	26
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	26
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	26
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	26
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	26
On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications	26
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	25
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	25
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	25
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	25
Development of GD-containing austenitic stainless steel	25
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	25
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	25
Tungsten fiber-reinforced tungsten composites and their thermal stability	25
Editorial Board	24
The oxidation of uranium diboride in flowing air atmospheres	24
Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	24
Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa	24
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	24
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	24
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	24
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	24
Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys	24
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	24

Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	24
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	24
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	23
Demonstration of industrially-fabricated plutonium disposition MOX	23
Ab initio molecular dynamics investigation of γ-(U,Zr) structural and thermal properties as a func	23
Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour	23
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy	23
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	23
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	23
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	23
Structural stability of β-phase uranium films at extreme temperatures	23
Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel	23
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	22
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	22
Achieving ultrahigh strength and high thermal stability of Cu-15 W composite by hierarchical structure with bimodal particle size distribution	22
Corrigendum to ‘Silver-phosphate glass matrix for iodine conditioning: From sorbent design to vitrification’	22
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	22
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	22
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	22
Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions	22
Oxidation and hydrolysis of thorium doped uranium nitride fuel for use in LWR	22
He clustering and role of vacancy in CuZr system	22
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	22
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	21
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds	21
Leaching of B-Si-glass by water in the presence of bentonite	21
Experimental estimation of radiation damage induced by 10B(n, α)7Li reactions in Al-B4C neutron absorber discharged from spent nuclear fuel pool	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
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	21
In-situ TEM observation of microstructure evolution in Fe9Cr1.5W0.4Si alloy during He+ irradiation and post-implantation annealing	21
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	21
Radiation damage in ion-irradiated CeO2 and (Ce, Gd)O2 sinters: Effect of the Gd content	21
Formation mechanisms of multilayered cobalt deposits on 304 stainless steel in primary cooling systems of pressurized water reactor nuclear power plants	21
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	21
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	21
Grain refinement and associated strengthening in laser additive repaired uranium	21
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	21
Mechanical and structural transformations of tungsten implanted with helium ions	20
Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization	20
The stability and behavior of Cr-rich α' precipitates under cascade damage in Fe-15Cr-8Al ternary alloys: An atomic-scale simulation study	20
Threshold parameters of vacuum arcs with W-fuzz cathodes	20
Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	20
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	20
Analytical W-H, H H and H He interatomic potentials for a W-H-He system	20
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	20
Deformation strengthening of uranium and dilute uranium alloys	20
Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors	20
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	20
Effect of He on the hardness and incipient plasticity of W films during nanoindentation	20
Finite temperature properties of uranium mononitride	20
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	20
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	20
Flow-Accelerated Corrosion and Wall Thinning Mechanism of a Dissimilar Metal Welded Joint in the Secondary Loop Piping System of Pressurized Heavy Water Reactors	20
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	20
Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes	20
Unveiling microstructure-property correlations in nuclear materials with high-energy synchrotron X-ray techniques	20
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions	20
High temperature zirconium alloys for fusion energy	20
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	19
A first principles study of zirconium grain boundaries	19
Evolution of β-Nb precipitates during hydrogenation of a zirconium-niobium alloy	19
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	19
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	19
Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	19
Hydrogen interaction with solid and liquid tin	19
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	19
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	19
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	19
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	19
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	19
Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt	19
Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	19
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	19
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	19
Corrosion resistance and material optimization in supercritical water oxidation for radioactive waste treatment	18
Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	18
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	18
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	18
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	18
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	18

Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	18
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	18
Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	18
Influence of long term Sodium Exposure on the Corrosion and Tensile Properties of AISI Type 316LN stainless steel and modified 9Cr-1Mo steel	18
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	18
Molecular dynamics study of fission gas behaviour and solubility in molten FLiNaK salt	18
Editorial Board	18
The effects of mixing multi-component HLW glasses on spinel crystal size	18
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys	18
The effect of Ti content on age hardening and mechanical properties of uranium-titanium alloys	18
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	18
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	18
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	17
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	17
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	17
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	17
Measurement of effective Sr diffusion coefficients in IG-110 graphite	17
Post-irradiation examination of U-7Mo/Mg and U-10Mo/Mg dispersion fuels irradiated in the NRU reactor	17
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	17
Effect of purity on the vacancy defects induced in self–irradiated tungsten: A combination of PAS and TEM	17
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	17
First-principles computational tensile tests of grain boundaries of zirconia with Cu segregation	17
The influence of nitrogen and nitrides on the structure and properties of proton irradiated ferritic/martensitic steel	17
Fabrication of fine-grained Li2TiO3 ceramic pebbles with enhanced crush load by rolling method: Optimization of Li/Ti ratio and sintering procedure	17
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	16
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	16
3D imaging and heat transfer simulation of the tritium breeding ceramic pebbles based on X-ray computed tomography (X-ray CT)	16
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	16
Kocks-Mecking-Estrin type model for high-temperature creep of Zircaloy-4	16
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	16
Segregation of Ni and Si to coherent bcc Fe-Cu interfaces from density functional theory	16
Radiation-enhanced diffusion of copper in iron studied by three-dimensional atom probe	16
Global and local texture development during initial plastic deformation of cold-pilgered Zircaloy-4 tubing	16
Crystal structure of U1-yLnyO2-x (Ln = Gd, Er) solid solution	16
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	16
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	16
Corrosion resistance of Ta-based TaCrWNbTi refractory high–entropy alloy coating in static lead–bismuth eutectic at 550 and 650℃ after 1000h	16
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	16
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	16
Trichloroethylene replacements for the cleaning of silicone oil used in the internal gelation process	16
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	16
Thermal properties measurement of TRISO particle coatings from room temperature to 900 °C using laser-based thermoreflectance methods	16
Deuterium retention in the elements of plasma facing components for the DEMO first wall	16
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	16
Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents	16
The quantitative 6H-SiC crystal damage depth profiling	16
Molecular-dynamics study of diffusional creep in uranium mononitride	16
Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures	16
Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2	16
Insights into stress corrosion crack growth of 316NG heat-affected zone in simulated PWR primary water	15
Enabling BWR fuel rod analysis in the BISON fuel performance code	15
Effective diffusivity of Ag and migration of Pd in IG-110 graphite	15
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	15
Eutectoid phase transformation in U-Mo-X alloys	15
Role of magnesium ions in modifying oxide growth rate on Zircaloy under breakaway corrosion regimes	15
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys	15
Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys	15
Damage microstructures in Ti3SiC2 under successive Xe-He-H ions irradiation and annealing process	15
Irradiation damage versus lattice distortion in AlNbTiVCrx (x = 0, 0.5, 1) high-entropy alloys from first-principles calculations and irradiation experiments	15
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe alloy	15
Effects of thermal aging on the stress corrosion cracking behavior of cast stainless steel with different δ-ferrite levels in high temperature water environment	15
Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation	15
How brittle is 'too brittle'?: Comparative mechanical assessment of silicon carbide and post-quench steam-oxidized zirconium alloy cladding	15
Editorial Board	15
Editorial Board	15
Impact of metallic Mo nanoparticles on the dissolution kinetics of UO2 in nitric acid under representative PUREX process conditions	15
Editorial Board	15
Micromechanical response of SiC-OPyC layers in TRISO fuel particles	15
The Effect of Proton Irradiation on In-situ Corrosion Behavior of Zr-Sn-Nb Zirconium Alloy under Simulated PWR Water Condition	15
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	15
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	15
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	15
Molecular dynamics study of primary damage in the near-surface region in nickel	15
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	15
Heat-treated additively manufactured and wrought 316L steels display a comparable response to ion irradiation	15
Simulation of defect build-up in tungsten during low energy irradiation	15
Characterization of the microstructure of yttrium hydride under proton irradiation	15
About the role of iron on the alteration of simplified nuclear glasses in deaerated solutions at 50°C	15
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt	15
Molecular dynamics simulation of bubble growth under surface of tungsten under helium irradiation	15
Environmentally-assisted cracking of electropolished 316L stainless steel in molten FLiNaK salt	15
Effect of free surfaces on localized plastic deformation in single-crystal nickel containing helium bubbles and radiation-induced self-interstitial atom clusters	15
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	15
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	15
Modelling of physical sputtering properties during tungsten fuzz growth under various impact energies on NAGDIS-II	15
Calculation of neutron-induced radiation damage to gold and lutetium-aluminium microstructures using MCNP6.2	15
Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles	14
Corrosion susceptibility and chromium loss in Austenitic steels and Nickel-based alloys in molten FLiNaK at 700 °C	14
Additive manufacturing of W/RAFM hypervapotron plasma-facing components and the steady state thermal fatigue behavior	14
Accelerated prediction of lattice thermal conductivity of Zirconium and its alloys: A machine learning potential method	14
Electrochemical recovery of Zr and Cd from molten chloride salts for reprocessing of used nitride fuels	14
The pores evolution in 3D view of nuclear graphite under ion beam irradiation	14
Defect annealing in heavy-ion irradiated tungsten: Long-time thermal evolution of saturated displacement damage at different temperatures	14
Significant suppression of void swelling and irradiation hardening in a nanograined/nanoprecipitated 14YWT-ODS steel irradiated by helium ions	14
Study of fusion boundary microstructure and local mismatch of SA508/alloy 52 dissimilar metal weld with buttering	14