Journal of Nuclear Materials

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	229
Editorial Board	110
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	76
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]	75
Effect of thermal oxidation on helium implanted pure iron	72
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	67
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	64
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	61
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	56
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	53
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	47
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	47
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements	45
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	43
Editorial Board	42
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	41
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	41
Annealing of the Raman defect peaks in He-implanted UO2	40
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	39
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	39
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	38
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	38
The incorporation of xenon at point defects and bubbles in uranium mononitride	38
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	36
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	35

Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	35
Raman spectroscopy of uranium nitride kernels	35
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	34
A molecular dynamics study of a cascade induced irradiation creep mechanism in pure copper	34
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	34
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	34
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	34
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	33
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	32
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	32
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	32
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	31
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	31
Development of GD-containing austenitic stainless steel	31
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	31
On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications	30
Thermal diffusion behavior of ternary UMoX alloys with Al coating	30
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	30
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	30
Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys	29
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	29
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	28
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	28
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
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	27
Effect of transmutation and active elements on the surface stability of silicon carbide	27
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	26
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	26
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	26
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	26
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	26
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	26
Tungsten fiber-reinforced tungsten composites and their thermal stability	26
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	26
Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa	25
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	25
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	25
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	25
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	25
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	25
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	25
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	25
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	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
Post-Irradiation Examination of AGR-3/4 TRISO Fuel Compacts Using Three-Dimensional X-ray Computed Tomography	24
Structural stability of β-phase uranium films at extreme temperatures	24
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	24
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	24
Editorial Board	24

Ab initio molecular dynamics investigation of γ-(U,Zr) structural and thermal properties as a func	24
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	24
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy	24
Corrigendum to ‘Silver-phosphate glass matrix for iodine conditioning: From sorbent design to vitrification’	24
Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions	24
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions	23
Achieving ultrahigh strength and high thermal stability of Cu-15 W composite by hierarchical structure with bimodal particle size distribution	23
Deformation strengthening of uranium and dilute uranium alloys	23
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	23
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	23
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	23
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds	23
He clustering and role of vacancy in CuZr system	23
Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors	22
Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	22
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	22
Mechanical and structural transformations of tungsten implanted with helium ions	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
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	22
Flow-Accelerated Corrosion and Wall Thinning Mechanism of a Dissimilar Metal Welded Joint in the Secondary Loop Piping System of Pressurized Heavy Water Reactors	22
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	22
Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization	22
Unveiling microstructure-property correlations in nuclear materials with high-energy synchrotron X-ray techniques	22
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	22
The oxidation of uranium diboride in flowing air atmospheres	22
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	22
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	22
Effect of He on the hardness and incipient plasticity of W films during nanoindentation	22
Threshold parameters of vacuum arcs with W-fuzz cathodes	22
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	22
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	22
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	21
Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour	21
Grain refinement and associated strengthening in laser additive repaired uranium	21
Finite temperature properties of uranium mononitride	21
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	21
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	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
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	20
Analytical W-H, H H and H He interatomic potentials for a W-H-He system	20
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	20
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	20
Demonstration of industrially-fabricated plutonium disposition MOX	20
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	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
Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel	20
Radiation damage in ion-irradiated CeO2 and (Ce, Gd)O2 sinters: Effect of the Gd content	20
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	20
Formation mechanisms of multilayered cobalt deposits on 304 stainless steel in primary cooling systems of pressurized water reactor nuclear power plants	20
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	20
Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes	20
Leaching of B-Si-glass by water in the presence of bentonite	20
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	20
High temperature zirconium alloys for fusion energy	20
Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	20
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	19
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	19
Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	19
The effects of mixing multi-component HLW glasses on spinel crystal size	19
Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	19
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	19
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	19
Editorial Board	19
Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	19
Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	19
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	19
Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	19
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	19
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys	19
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	18
Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt	18
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	18
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	18
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	18
Molecular dynamics study of fission gas behaviour and solubility in molten FLiNaK salt	18
Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents	18
Global and local texture development during initial plastic deformation of cold-pilgered Zircaloy-4 tubing	18
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	18
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	18
Trichloroethylene replacements for the cleaning of silicone oil used in the internal gelation process	18

Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	18
Kocks-Mecking-Estrin type model for high-temperature creep of Zircaloy-4	18
3D imaging and heat transfer simulation of the tritium breeding ceramic pebbles based on X-ray computed tomography (X-ray CT)	18
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	18
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	18
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	18
The effect of Ti content on age hardening and mechanical properties of uranium-titanium alloys	18
First-principles computational tensile tests of grain boundaries of zirconia with Cu segregation	18
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	17
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	17
Irradiation damage versus lattice distortion in AlNbTiVCrx (x = 0, 0.5, 1) high-entropy alloys from first-principles calculations and irradiation experiments	17
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	17
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	17
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	17
Hydrogen interaction with solid and liquid tin	17
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	17
Segregation of Ni and Si to coherent bcc Fe-Cu interfaces from density functional theory	17
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	17
Corrosion resistance of Ta-based TaCrWNbTi refractory high–entropy alloy coating in static lead–bismuth eutectic at 550 and 650℃ after 1000h	17
Evolution of β-Nb precipitates during hydrogenation of a zirconium-niobium alloy	17
Fabrication of fine-grained Li2TiO3 ceramic pebbles with enhanced crush load by rolling method: Optimization of Li/Ti ratio and sintering procedure	17
Molecular-dynamics study of diffusional creep in uranium mononitride	17
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	17
The influence of nitrogen and nitrides on the structure and properties of proton irradiated ferritic/martensitic steel	17
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	17
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	16
A first principles study of zirconium grain boundaries	16
Corrosion resistance and material optimization in supercritical water oxidation for radioactive waste treatment	16
Corrosion susceptibility and chromium loss in Austenitic steels and Nickel-based alloys in molten FLiNaK at 700 °C	16
Additive manufacturing of W/RAFM hypervapotron plasma-facing components and the steady state thermal fatigue behavior	16
Fabrication and conductivity of zirconium doped Li2TiO3 tritium breeder	16
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	16
Crystal structure of U1-yLnyO2-x (Ln = Gd, Er) solid solution	16
Post-irradiation examination of U-7Mo/Mg and U-10Mo/Mg dispersion fuels irradiated in the NRU reactor	16
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	16
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	16
Effect of purity on the vacancy defects induced in self–irradiated tungsten: A combination of PAS and TEM	16
Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures	16
Influence of long term Sodium Exposure on the Corrosion and Tensile Properties of AISI Type 316LN stainless steel and modified 9Cr-1Mo steel	16
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	16
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	16
Micromechanical response of SiC-OPyC layers in TRISO fuel particles	16
Accelerated prediction of lattice thermal conductivity of Zirconium and its alloys: A machine learning potential method	16
Role of magnesium ions in modifying oxide growth rate on Zircaloy under breakaway corrosion regimes	16
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	16
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	16
Thermal properties measurement of TRISO particle coatings from room temperature to 900 °C using laser-based thermoreflectance methods	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
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	16
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	16
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	16
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	16
Deuterium retention in the elements of plasma facing components for the DEMO first wall	16
Effects of surface treatments and temperature on the oxidation behavior of 308L stainless steel cladding in hydrogenated high-temperature water	16
Insights into stress corrosion crack growth of 316NG heat-affected zone in simulated PWR primary water	16
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	16
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	16
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe alloy	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
Radiation-enhanced diffusion of copper in iron studied by three-dimensional atom probe	16
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	16
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	16
Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen	15
Molecular dynamics study of primary damage in the near-surface region in nickel	15
Effect of radial hydrides on fracture behavior of Zr-2.5Nb pressure tube material	15
Eutectoid phase transformation in U-Mo-X alloys	15
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	15
Editorial Board	15
Editorial Board	15
Solid-state welding for dissimilar zirconium alloy under joule heating effect: Material flowing behavior, characteristics, evolution and formation of interface	15
Corrosion of 316H stainless steel in flowing FLiNaK salt	15
Study of fusion boundary microstructure and local mismatch of SA508/alloy 52 dissimilar metal weld with buttering	15
Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics	15
Calculation of neutron-induced radiation damage to gold and lutetium-aluminium microstructures using MCNP6.2	15
Editorial Board	15
Enabling BWR fuel rod analysis in the BISON fuel performance code	15
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt	15
Irradiation-induced chemical disordering in ceramics: The case of SiC	15
Heat-treated additively manufactured and wrought 316L steels display a comparable response to ion irradiation	15
Modelling of physical sputtering properties during tungsten fuzz growth under various impact energies on NAGDIS-II	15
Evolution of microstructure and mechanical properties of ZrC reinforced FeCrAl alloy after Fe-ions irradiation	15
Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation	15
Deterioration of irradiation resistance of ODS-F/M steel under high concentration of helium	15
Impact of metallic Mo nanoparticles on the dissolution kinetics of UO2 in nitric acid under representative PUREX process conditions	15
LIBS analysis of tritium in thin film-type samples	15
Significant suppression of void swelling and irradiation hardening in a nanograined/nanoprecipitated 14YWT-ODS steel irradiated by helium ions	15
About the role of iron on the alteration of simplified nuclear glasses in deaerated solutions at 50°C	15
Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys	15
Modification of the Cement Matrix with Organic Additives for Stabilizing Pertechnetate Ions	15
Characterization of zirconium carbide microspheres synthesized via internal gelation	15
Editorial Board	15
Effect of free surfaces on localized plastic deformation in single-crystal nickel containing helium bubbles and radiation-induced self-interstitial atom clusters	15
Helium interaction with solutes and impurities in neutron-irradiated nanostructured ferritic alloys: A first principles study	15
Enhancement of mechanical properties by repeated heat treatment in reduced activation ferritic/martensitic steel with Ta and Ti	15
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys	15