Journal of Nuclear Materials

Article	Citations
Editorial Board	198
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]	89
Effect of thermal oxidation on helium implanted pure iron	70
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	65
He nanobubble driven W surface growth during low-energy He ion irradiations	64
Dose-dependent strain localization and embrittlement in ferritic materials: A predictive approach based on sub-grain plasticity modelling	57
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	57
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium	56
In-situ ion irradiation study of alloy 709 stainless steels with different processing histories	54
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	53
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	53
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	47
Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa	46
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	43
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	40
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	39
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	39
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	37
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	37
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	36
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	36
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	35
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	34
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	34
Development of GD-containing austenitic stainless steel	32

Effect of transmutation and active elements on the surface stability of silicon carbide	32
Helium causing disappearance of a/2<111> dislocation loops in binary Fe-Cr ferritic alloys	32
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	31
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	31
Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten	31
Raman spectroscopy of uranium nitride kernels	30
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	30
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	30
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	30
The incorporation of xenon at point defects and bubbles in uranium mononitride	30
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	29
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	29
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	28
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	28
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	28
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	28
Evaluation of the anisotropic grain boundaries and surfaces of α-U via molecular dynamics	28
A molecular dynamics study of a cascade induced irradiation creep mechanism in pure copper	27
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	27
Annealing of the Raman defect peaks in He-implanted UO2	27
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	27
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	27
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	27
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	27
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	27
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements	27
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	27
Effects of TiC nanoparticle additions on microstructure and mechanical properties of FeCrAl alloys prepared by directed energy deposition	26
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	26
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	26
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	26
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	26
Tungsten fiber-reinforced tungsten composites and their thermal stability	25
On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications	25
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	25
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	25
Mechanical and structural transformations of tungsten implanted with helium ions	24
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	24
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	24
Unveiling microstructure-property correlations in nuclear materials with high-energy synchrotron X-ray techniques	24
Editorial Board	24
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	24
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	24
Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes	24
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	24
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	24
Evaluation of Sb-Nd and Te-Nd phases within the U-Zr fuel matrix and their interactions with HT9 alloy	23
Oxidation and hydrolysis of thorium doped uranium nitride fuel for use in LWR	23
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	23
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	23

Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions	23
Structural stability of β-phase uranium films at extreme temperatures	23
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	23
Threshold parameters of vacuum arcs with W-fuzz cathodes	23
Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products	23
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	22
Radiation damage in ion-irradiated CeO2 and (Ce, Gd)O2 sinters: Effect of the Gd content	22
In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound	22
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	22
Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	22
The stability and behavior of Cr-rich α' precipitates under cascade damage in Fe-15Cr-8Al ternary alloys: An atomic-scale simulation study	22
Analytical W-H, H H and H He interatomic potentials for a W-H-He system	22
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	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
He clustering and role of vacancy in CuZr system	22
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	21
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions	21
Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	21
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	21
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	21
High-quality graphene as a coating for polycrystalline tungsten in low-energy helium and deuterium plasma exposures	21
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	21
Deformation strengthening of uranium and dilute uranium alloys	21
Grain refinement and associated strengthening in laser additive repaired uranium	21
Corrigendum to ‘Silver-phosphate glass matrix for iodine conditioning: From sorbent design to vitrification’	21
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	21
The oxidation of uranium diboride in flowing air atmospheres	21
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	21
Finite temperature properties of uranium mononitride	21
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	20
Demonstration of industrially-fabricated plutonium disposition MOX	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
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	20
In-situ TEM observation of microstructure evolution in Fe9Cr1.5W0.4Si alloy during He+ irradiation and post-implantation annealing	20
Effect of He on the hardness and incipient plasticity of W films during nanoindentation	20
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	20
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	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
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	20
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	19
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	19
Macroscopic and microscopic element distribution in transition zones of GTAW Alloy 52M weld joint and its PWSCC growth behaviour	19
Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	19
Crystal structure of U1-yLnyO2-x (Ln = Gd, Er) solid solution	19
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	19
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	19
High temperature zirconium alloys for fusion energy	19
Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization	19
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	19
Editorial Board	19
Evolution of β-Nb precipitates during hydrogenation of a zirconium-niobium alloy	19
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	19
Ab initio molecular dynamics investigation of γ-(U,Zr) structural and thermal properties as a func	19
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	19
Short communication: Characterization of Mo-rich precipitates in δ-ferrite of thermally aged Mo-bearing cast austenitic stainless steel	19
Editorial Board	19
The effects of mixing multi-component HLW glasses on spinel crystal size	19
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	18
First-principles computational tensile tests of grain boundaries of zirconia with Cu segregation	18
Post-irradiation examination of U-7Mo/Mg and U-10Mo/Mg dispersion fuels irradiated in the NRU reactor	18
Kocks-Mecking-Estrin type model for high-temperature creep of Zircaloy-4	18
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	18
The influence of nitrogen and nitrides on the structure and properties of proton irradiated ferritic/martensitic steel	18
Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	18
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	18
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	18
Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	18
Segregation of Ni and Si to coherent bcc Fe-Cu interfaces from density functional theory	18
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	18
Corrigendum to “Fabrication and characterization of crushed titanium-beryllium intermetallic compounds” [Journal of Nuclear Materials 498 (2018) 249-253]	18
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe alloy	18
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	18
Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	18
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	18
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	18
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	18
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	18
Deuterium retention in the elements of plasma facing components for the DEMO first wall	18
Fabrication of fine-grained Li2TiO3 ceramic pebbles with enhanced crush load by rolling method: Optimization of Li/Ti ratio and sintering procedure	18
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	17

The effect of Ti content on age hardening and mechanical properties of uranium-titanium alloys	17
Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents	17
Hydrogen interaction with solid and liquid tin	17
Accident tolerant fuel rod failure under low stress: A case study of BWR under station blackout using Bison	17
3D imaging and heat transfer simulation of the tritium breeding ceramic pebbles based on X-ray computed tomography (X-ray CT)	17
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	17
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	17
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	17
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	17
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	17
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	17
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	17
Measurement of effective Sr diffusion coefficients in IG-110 graphite	17
The statistical ductility of embrittled Zircaloy-4 and its regulatory implications	17
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	17
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	16
Molecular dynamics study of fission gas behaviour and solubility in molten FLiNaK salt	16
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	16
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	16
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	16
The quantitative 6H-SiC crystal damage depth profiling	16
A first principles study of zirconium grain boundaries	16
Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	16
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	16
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	16
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	16
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	16
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	16
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	16
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	16
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	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
Irradiation damage versus lattice distortion in AlNbTiVCrx (x = 0, 0.5, 1) high-entropy alloys from first-principles calculations and irradiation experiments	16
Global and local texture development during initial plastic deformation of cold-pilgered Zircaloy-4 tubing	16
Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt	16
Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	16
Thermal properties measurement of TRISO particle coatings from room temperature to 900 °C using laser-based thermoreflectance methods	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
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	16
Radiation-enhanced diffusion of copper in iron studied by three-dimensional atom probe	16
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	16
Trichloroethylene replacements for the cleaning of silicone oil used in the internal gelation process	16
Validating modern methods for impurity analysis in fluoride salts	16
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	16
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	15
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	15
Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91	15
Role of chemical disorder on radiation-induced defect production and damage evolution in NiFeCoCr	15
Accelerated prediction of lattice thermal conductivity of Zirconium and its alloys: A machine learning potential method	15
Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation	15
Characterization of zirconium carbide microspheres synthesized via internal gelation	15
Editorial Board	15
Modeling of hydride reorientation in E110 during thermal cycling	15
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	15
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	15
Fabrication and thermal conductivity of UN-UB2 composites fabricated by spark plasma sintering	15
The Effect of Proton Irradiation on In-situ Corrosion Behavior of Zr-Sn-Nb Zirconium Alloy under Simulated PWR Water Condition	15
Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings	15
Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics	15
Effective diffusivity of Ag and migration of Pd in IG-110 graphite	15
UO2 solubility and chemical interactions in molten LiCl-Li2O	15
The pores evolution in 3D view of nuclear graphite under ion beam irradiation	15
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	15
Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2	15
Thermodynamic investigations of fuel-cladding chemical interaction in U-5Fs and U-10Zr metallic fuels with the TAF-ID	15
Effects of thermo-mechanical process on phase transitions, hydrogen solubility and corrosion of Ta-modified Zr-1Nb alloys	15
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	15
About the role of iron on the alteration of simplified nuclear glasses in deaerated solutions at 50°C	15
Modification of the Cement Matrix with Organic Additives for Stabilizing Pertechnetate Ions	15
Electrochemical recovery of Zr and Cd from molten chloride salts for reprocessing of used nitride fuels	15
Editorial Board	15
Editorial Board	15
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	15
Damage microstructures in Ti3SiC2 under successive Xe-He-H ions irradiation and annealing process	14
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	14
Environmentally-assisted cracking of electropolished 316L stainless steel in molten FLiNaK salt	14
Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen	14
Simulation of defect build-up in tungsten during low energy irradiation	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
Phonon modal analysis of thermal transport in ThO2 with point defects using equilibrium molecular dynamics	14
Ultrafast diffusion of overpressurized gas filled nanobubbles in UO2	14
Contributions of Ni-content and irradiation temperature to the kinetic of solute cluster formation and consequences on the hardening of VVER materials	14
Study of fusion boundary microstructure and local mismatch of SA508/alloy 52 dissimilar metal weld with buttering	14
Helium interaction with solutes and impurities in neutron-irradiated nanostructured ferritic alloys: A first principles study	14
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	14
Characterization of the microstructure of yttrium hydride under proton irradiation	14
Micromechanical response of SiC-OPyC layers in TRISO fuel particles	14
Molecular dynamics study of primary damage in the near-surface region in nickel	14
On the influence of specimen size and geometry on the fracture toughness of tungsten heavy metal alloys	14
Molecular dynamics simulation of bubble growth under surface of tungsten under helium irradiation	14
Additive manufacturing of W/RAFM hypervapotron plasma-facing components and the steady state thermal fatigue behavior	14
Heat-treated additively manufactured and wrought 316L steels display a comparable response to ion irradiation	14
Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys	14
An atom probe study on the Fe distribution in Zr-based alloys with different Fe content under high fluence neutron irradiation	14