Journal of Nuclear Materials

Article	Citations
Impact of anisotropic grain microstructure on the fracture-mechanical properties of ITER grade tungsten plate	263
Editorial Board	129
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	76
Editorial Board	61
Finite element analysis of the stress state and fracture in the TRISO-particle buffer layer	58
The incorporation of xenon at point defects and bubbles in uranium mononitride	57
Ductility evaluation of nitrided Zircaloy-4 cladding by ring compression testing	56
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	56
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	53
A comprehensive atomistic investigation on the cascade induced helium bubble motion in bcc iron for neutron irradiated RAFM steels	51
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	49
Effect of thermal oxidation on helium implanted pure iron	48
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	47
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	46
Inter-diffusion of nitrogen and helium in IG-110 nuclear graphite	44
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	42
Anisotropy study of hydrogen diffusion along different directions of Zr-2.5%Nb alloy pressure tube using neutron imaging	40
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	40
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments	39
Effect of transmutation and active elements on the surface stability of silicon carbide	37
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	36
Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation	36
Raman spectroscopy of uranium nitride kernels	35
The shear stress required for the splitting of a helical dislocation into a prismatic dislocation loop and a screw dislocation in alpha-iron	34
Tritium release performance of centrifugally granulated Li2TiO3 pebbles	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]	33
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	32
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	31
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	31
Tungsten fiber-reinforced tungsten composites and their thermal stability	30
Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms	30
Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	30
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	29
A deep learning interatomic potential model for the generation and evolution mechanisms of irradiation defects in yttrium hydride	29
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	29
Influence of Cu/W semi-coherent interfacial structure on helium behavior: insights from atomistic simulations	29
Performance of high-Cr ODS steels under high-temperature neutron irradiation	29
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	29
Post-irradiation examination of AGR-3/4 TRISO fuel compacts using three-dimensional X-ray computed tomography	29
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	28
Evidence of radiation induced segregation clustering in binary ferritic model alloys	28
Chromium doping effects on UO2 grain boundary chemistry: A combined experimental and modeling approach	28
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	28
Development of GD-containing austenitic stainless steel	28
Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches	27
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	27
Study on the preparation of highly efficient iodine capture activated carbon via dehydration of NH4H2PO4 combined with CO2 activation and its adsorption mechanism	27
Thermal diffusion behavior of ternary UMoX alloys with Al coating	27
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	27
Effect of Y2O3 addition on the microstructure and liquid LBE cavitation erosion behaviors of Fe-Cr-Al-Ti-C-xY2O3 laser clade coatings	27
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	27
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	27
First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment	27
Waste acceptance criteria testings of a phosphate-based geopolymer waste form to immobilize radioactive borate waste	27
Assessing the Role of Thermal Gradients in Abnormal Grain Growth of Tungsten Under Fusion-Relevant Conditions	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	26
The vacancy-mediated diffusion of transition metal solutes in tungsten: Atomic Kinetic Monte Carlo simulations	25
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	25
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	25
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	25
Effect of point defects on water adsorption on the ThO2{111} surface: A first-principles computational study	25
Wire and arc additive manufacturing fabrication of ODS-RAFM steels and preliminary evaluation on microstructures and mechanical properties	25
Defect Formation and Transmutation Behaviors in Irradiated Tungsten under Thermal-neutron Shielded and Mixed Spectrum Conditions	25
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	25
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	25
Tailoring the radiation induced dislocation loop behavior in the FeCoNiCr alloy via minor alloying strategy	24
Corrosion behavior of 316H stainless steel in molten LiF-UF4 and LiF-UF4-ZrF4 salts	24
The evolution of NiMnSi clusters in RPV steels under proton irradiation: The effect of Cu	24
Development of novel multi-element low-activation Fe-based alloys for nuclear and fusion reactor applications	24
Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation	24
Editorial Board	23
Sink effect on the microstructural evolution of defect clusters in Mo-Nb alloys during in-situ He ion irradiation	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
Formation mechanisms of multilayered cobalt deposits on 304 stainless steel in primary cooling systems of pressurized water reactor nuclear power plants	23

Structural stability of β-phase uranium films at extreme temperatures	23
Exploring irradiation-induced HCP to FCC phase transformation in a micro-grained zirconium alloy	23
Effects of vapor hydration and radiation on the leaching behavior of nuclear glass	23
Behaviour of fission products in UO2: Experimental characterization of the Cs-I-UO2 model system at high temperature	22
Deuterium behavior in tungsten following declining-temperature plasma exposures in two temperature ranges	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
Regulation mechanism of corrosion resistance in uranium-niobium-zirconium alloys: synergistic and concentration-dependent effects of alloying elements	22
Synergistic effects of hydrogen and helium on He bubble evolution in bcc-iron: A kinetic model	22
Application of the immobilized low-activity waste glass corrosion model to the static dissolution of 24 statistically-designed alkali-borosilicate waste glasses	22
First-principles investigation of the interaction between oxygen and alloy atoms in α-zirconium	21
Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys	21
In-situ TEM investigation of recovery mechanisms in ion-irradiated ITER-grade tungsten	21
Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization	21
Demonstration of industrially-fabricated plutonium disposition MOX	21
Modeling of flux-dependent fluence effect on in-reactor deformation in Zr-alloy tubes	21
Atomistic mechanism of activation controlled liquid metal corrosion at the Fe-Pb interface	21
Effect of microstructure on the delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tube	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
Thermal shock resistance of nanocrystalline and ultrafine-grained W-Y2O3-Ti alloys	21
Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water	21
Buffering the oxygen activity of uranium dioxide fuels using niobium and molybdenum as redox additives	21
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup	21
Tensile properties of co-rolled Zr/U-10Mo fuel at ambient and elevated temperatures	21
Achieving ultrahigh strength and high thermal stability of Cu-15 W composite by hierarchical structure with bimodal particle size distribution	21
Some observations on the habit plane of hydride plates precipitated in Zr-2.5Nb pressure tubes	21
Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application	21
Corrigendum to ‘Silver-phosphate glass matrix for iodine conditioning: From sorbent design to vitrification’	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
Radiation damage in ion-irradiated CeO2 and (Ce, Gd)O2 sinters: Effect of the Gd content	20
Identification of irradiation-induced phases in thermomechanically strengthened P92 steel after Fe ion irradiation at 700℃	20
Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C	20
Precipitation characteristics and growth mechanism of Fe and Cr from liquid lead-bismuth eutectic by quenching in liquid nitrogen	20
Deformation strengthening of uranium and dilute uranium alloys	20
Grain refinement and associated strengthening in laser additive repaired uranium	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
Interface alloying design to improve the stability and cohesion of W/HfC interface by first-principles study	20
Deuterium behavior in pristine and pre-damaged tungsten under plasma exposure at a rising or declining temperature	19
"Exploring the role of lithium in Al2O3 tritium permeation barrier development: A crucial challenge for fusion reactor progress"	19
The oxidation of uranium diboride in flowing air atmospheres	19
Effect of trace Al and Ti elements on borosilicate glass corrosion resistance of Inconel 690 alloy	19
Threshold parameters of vacuum arcs with W-fuzz cathodes	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
Oxygen potential and oxygen diffusion data for guiding the manufacture of MOX fuel for fast neutron reactors	19
Development of a neural network potential for osmium enables irradiation damage simulations	19
Impact of PKA energy and spatial correlation of primary damage on irradiation microstructure evolution in iron: An object kinetic Monte Carlo simulation	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
Immobilization of simulated An4+ in radioactive sludge via microwave sintering: Mechanistic and performance	18
Leaching of B-Si-glass by water in the presence of bentonite	18
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds	18
Deuterium permeation performance of V4Cr4Ti/RAFM steel joint with in-situ formed carbide interlayer during diffusion bonding	18
Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing	18
Editorial Board	18
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions	18
He clustering and role of vacancy in CuZr system	18
Finite temperature properties of uranium mononitride	18
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	18
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel	18
Hydrogen interaction with solid and liquid tin	18
Damage thresholds revealed by ions emitted from boron nitride and tungsten exposed to energetic photons at high dose rates	18
Assessment of EUROFER97, tungsten and CuCrZr alloy transmutation effects under IFMIF-DONES and DEMO conditions	18
Interpretation of dissolution behavior at the surface of uranium-zirconium oxide solid solutions	18
Manufacturing Oxide Dispersion Strengthened (ODS) steel plate via cold spray and friction stir processing	18
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys	18
Investigations of size effect and normalization models for tensile deformation of A508-III steel miniature specimens	18
Hydrogen diffusion on the tin-covered tungsten surface: A first-principles study	18
Microstructure-based crack formation in tungsten exposed to cyclic transient heating	17
Atomistic investigation on grain boundary effect on helium segregation and clustering in iron	17
Predictive phase stability of actinide-bearing hollandite waste forms from first-principles calculations	17
Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond	17
Interaction of face-centered cubic phase and twin in Zr–1.0Sn–1.0Nb–0.3Fe 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
Irradiation-condition dependent mechanisms controlling buffer densification and fracture in TRISO nuclear fuel particles	17
Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel	17
Structural, electronic, elastic and thermal properties of Cr-doped U3Si2: A DFT study	17
Modelling the growth and evolution of statistically significant populations of intergranular fission gas bubbles by IPM	17
In-pile heat conduction model of the dispersion nuclear fuel plate with particle agglomeration. Part II: Predicting the effective thermal conductivity under the in-pile thermal transfer pattern based	17
Influence of long term Sodium Exposure on the Corrosion and Tensile Properties of AISI Type 316LN stainless steel and modified 9Cr-1Mo steel	17
Cohesion properties and irradiation tolerance of W-Fe graded interfaces from molecular dynamics simulation	17

Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions	17
Effect of radiation damage on liquid Pb corrosion at the Fe/Pb solid-liquid interface	17
Thermal properties measurement of TRISO particle coatings from room temperature to 900 °C using laser-based thermoreflectance methods	17
Editorial Board	17
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment	16
Editorial Board	16
Density functional theory calculations of the mixing enthalpy of ternary uranium carbide compounds	16
Influence of multi-ion concentrations on corrosion product deposition on zirconium alloy cladding in high-temperature water	16
Molecular dynamics simulation of phonon thermal conductivity variation in E110 alloy post operation in VVER-type reactor irradiation conditions	16
He bubbles inhibition and abnormal hardening in GH3535 alloy by niobium element addition	16
Characterization of the role of heat-treatment on the microstructure and texture evolution of Zr-2.5 %Nb Alloy	16
Corrosion resistance of Ta-based TaCrWNbTi refractory high–entropy alloy coating in static lead–bismuth eutectic at 550 and 650℃ after 1000h	16
Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV	16
Chemical characterization of uniform and localized oxides formed on Zr-2.5 (wt. %) Nb alloy	16
Significant amplification of irradiation dose effects by hydrogen-helium and the mechanism based on rate theory	16
First-principles study of elastic and thermodynamic properties of UO2, γ-UO3 and α-U3O8	16
Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures	16
Review of hydrogen-induced mechanical degradation in uranium and uranium alloys	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
Microstructure evolution of a Cr-Cr/Mo coated Zr alloys in inert gas and steam environment at high temperature	16
Morphology-governed rheology of RuO2 in borosilicate glass melts: Network formation and shear-thinning behavior	16
Thermal desorption of tritium and helium from lithium ceramics Li2TiO3+5mol% TiO2 after neutron irradiation	16
A first principles study of zirconium grain boundaries	16
Performance of Sc-Y-ODS variant of Eurofer steel in stagnant PbLi at 600°C	16
STEM and HRTEM study on matrix microstructure and oxide particles in 11Cr ferritic/martensitic ODS steel	16
Deuterium retention in the elements of plasma facing components for the DEMO first wall	16
Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals	16
Reducing the oxidation rate of Cr-coated Zr alloys under high temperature steam environment: An approach of an outer Zr coating	16
Influence of transmutation-induced Re/Os content on defect evolution in neutron-irradiated W	15
Molecular-dynamics study of diffusional creep in uranium mononitride	15
Development of a coupling facility for high-energy proton irradiation and high-temperature high-pressure water corrosion	15
The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study	15
Atomistic mechanisms of hydrogenation corrosion resistance in representative uranium nitrides via ab initio molecular dynamics simulations	15
Diffusion behaviors of HF in molten LiF-BeF2 and LiF-NaF-KF eutectics studied by FPMD simulations and electrochemical techniques	15
Preparation of ZrC coating in TRISO fuel particles by precise transportation of solid precursor and its microstructure evolution	15
Prediction of thermal conductivity in UO2 with SiC additions and related decisive features discovery	15
Mitigating the oxidation and carburization in austenitic stainless steels exposed to supercritical carbon dioxide by Al addition: the working mechanism	15
Numerical simulation study on the impact of helium bubbles on hydrogen isotope retention behavior in tungsten	15
Helium plasma irradiation induced morphology evolution and sputtering behavior in WTaTiVCr refractory high entropy alloy and tungsten	15
Structural and transport properties of the molten salt NaCl-KCl-UCl3 using the polarizable ion model	15
Influence of platinum group metal particle aggregation on the rheological behavior of a glass melt	15
X-site element dependence of radiation resistance in Zr2SeC and Zr2SeP covalent MAX phases	15
Deuterium retention in W-Cr-Y alloy: Impact of the manufacturing method and helium presence	15
Simulations of grain growth in tungsten armor materials under ARC plasma edge operation conditions using an integrated plasma-edge/materials model	15
Microstructural changes and irradiation hardening behavior of V-4Cr-4Ti alloys irradiated with He ions using flash-electropolishing	15
Post-quench ductility limits of coated ATF with various zirconium-based alloys and coating designs	15
Comparative analysis of the long-term strength of Russian ferritic-martensitic reactor steels	15
Microstructure, thermal properties and irradiation behaviors of uranium nitride (UN) nuclear fuel densified by Spark Plasma Sintering (SPS)	15
Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study	15
Molecular dynamics study of fission gas behaviour and solubility in molten FLiNaK salt	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
Insights on the structure and properties of sodium iron phosphate glasses from molecular dynamics simulations	15
Irradiation damage versus lattice distortion in AlNbTiVCrx (x = 0, 0.5, 1) high-entropy alloys from first-principles calculations and irradiation experiments	15
Oxygen potential of neodymium-doped U0.817Pu0.180Am0.003O2± uranium–plutonium–americium mixed oxides at 1573, 1773, and 1873K	15
Corrosion resistance and material optimization in supercritical water oxidation for radioactive waste treatment	15
Molecular dynamics study of primary damage in the near-surface region in nickel	14
Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys	14
Multiscale, mechanistic modeling of irradiation-enhanced silver diffusion in TRISO particles	14
Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation	14
Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys	14
Editorial Board	14
Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings	14
The effect of microstructure evolution on fatigue property of SA508Gr.4N steel for nuclear reactor pressure vessels	14
Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions	14
Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings	14
Microstructural evolution of ion-irradiated commercially pure titanium	14
Molecular dynamics simulation of bubble growth under surface of tungsten under helium irradiation	14
Corrosion study of zirconium alloys via molecular dynamics simulations: I. oxygen migration in zirconium oxides under low-dose irradiation induced displacement damage	14
Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations	14
Recent studies to the impact of a ceramic breeder environment on the mechanical properties of EUROFER97 under operating conditions	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
Effect of free surfaces on localized plastic deformation in single-crystal nickel containing helium bubbles and radiation-induced self-interstitial atom clusters	14
Editorial Board	14
About the role of iron on the alteration of simplified nuclear glasses in deaerated solutions at 50°C	14
An atom probe study on the Fe distribution in Zr-based alloys with different Fe content under high fluence neutron irradiation	14
Micromechanical response of SiC-OPyC layers in TRISO fuel particles	14
Insights into stress corrosion crack growth of 316NG heat-affected zone in simulated PWR primary water	14
UO2 solubility and chemical interactions in molten LiCl-Li2O	14
Variations in the contents of crystalline phases in the Chornobyl lava specimen	14
Coordination-driven mixing behavior of corrosion and fission products in NaCl-UCl₃ molten salt	14
Contributions of Ni-content and irradiation temperature to the kinetic of solute cluster formation and consequences on the hardening of VVER materials	14
Role of chemical disorder on radiation-induced defect production and damage evolution in NiFeCoCr	14
Editorial Board	14
Phonon modal analysis of thermal transport in ThO2 with point defects using equilibrium molecular dynamics	14
Role of magnesium ions in modifying oxide growth rate on Zircaloy under breakaway corrosion regimes	14
Poisitron annihilation study on corrosion-incudced defects in UNS N10003 alloy exposed to tellurium-containing FLiNaK salt	14
Selective recovery of rare earth fps from radioactive molten salts using liquid in-sn alloy cathodes and real-time monitoring techniques	14
Impact of metallic Mo nanoparticles on the dissolution kinetics of UO2 in nitric acid under representative PUREX process conditions	14
Irradiation-induced chemical disordering in ceramics: The case of SiC	13
Characterization of the microstructure of yttrium hydride under proton irradiation	13
A combined experimental and theoretical study of small and large vacancy clusters in tungsten	13
Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics	13
Environmentally-assisted cracking of electropolished 316L stainless steel in molten FLiNaK salt	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