Journal of Nuclear Materials

Article	Citations
Response of oxide nano-particles to helium ion irradiation in oxide dispersion strengthened steels with CeO2 and Y2O3 additions	164
Elevated tritium diffusion barrier from varied segregation strengths in Li4TiO4 (1–10) grain boundary	122
Ab initio study of neutral point defect properties in 6H-SiC based on the SCAN functional	68
Corrigendum to “Non-electric mass transfer between stainless steel 316H and glassy carbon in NaF-KF-UF4 salt” [Journal of Nuclear Materials 604 (2025) 155534]	60
Radiation damage study of POCO ZXF-5Q graphite for neutrino production targets using 4.5 MeV helium ions	56
Investigating the interactions between hydrotalcite and U(IV) nanoparticulates	54
In-situ TEM characterization of dislocation loops in tungsten under simultaneous helium and hydrogen irradiation	54
The role of microstructural evolution in irradiation hardening of Alloy 718 under low dose proton irradiation	54
Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy	54
Neutron flux impact on rate of expansion of quartz	53
Dispersed barrier hardening modeling on depth-distributed helium bubbles in iron-based alloys	52
Insight into threshold creep behaviour in Zr-2.5Nb alloy	50
Fracture behavior and grain boundary cohesion of alumina scales formed on ion-irradiated FeCrAl-ODS alloy	49
Radiation damage of Ceria and Ceria-gadolinia mixed oxides: effect of the Gd content and Ion stopping power	45
New insights into the carburization and tensile behavior of superalloys Inconel 617 and Incoloy 800H in helium containing trace methane at 950 °C	44
Ab initio study of helium in titanium beryllides	42
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	40
Hydrogen permeability of non-stoichiometric tungsten oxides	40
Effect of the cycle number on fretting wear behavior of alloy 690TT tube in high-temperature pressurized water	39
An improved analysis of small punch deformation for evaluating tensile properties	39
Measurement of local mechanical properties for Cr-coated accident tolerant fuel cladding	39
Evaluation of the anisotropic grain boundaries and surfaces of α-U via molecular dynamics	38
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor	37
Correlation between impact angle and corrosion-erosion damage behavior of ferritic/martensitic steel exposed to flowing oxygen-saturated lead-bismuth eutectic	36
Diffusion behavior of oxygen in the electro-deoxidation of uranium oxide in LiCl-rich melt	35

Modelling the brittle-to-ductile transition of high-purity tungsten under neutron irradiation	35
Parameterization of vacancy production rate in phase-field models of fission gas bubble evolution in nuclear fuel	34
Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications	34
High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer	34
Exploring the inhibitory effect of WTaVCr high-entropy alloys on hydrogen retention: From dissolution, diffusion to desorption	34
Hydrogen diffusion in zirconium cladding alloys with an inner liner as quantified by neutron radiography and nanoindentation	33
Efficient atomistic simulations of radiation damage in W and W–Mo using machine-learning potentials	33
Parametrization of embedded-atom method potential for liquid lithium and lead-lithium eutectic alloy	32
Self–ion irradiation of high purity iron: Unveiling plasticity mechanisms through nanoindentation experiments and large-scale atomistic simulations	32
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties	31
Editorial Board	31
Grain growth kinetics of the gamma phase metallic uranium	30
Evaluation of the delayed hydrogen cracking behavior and the hydrogen diffusion coefficient for different microstructures of the Zr-2.5%Nb alloy	29
Editorial Board	29
Precipitation of Cr-rich clusters in Fe-Cr alloys: Effects of irradiation from first principles modeling and experimental observations	29
On the origin of the hydride precipitation-dissolution hysteresis in zirconium: Comments on Short Communication of G.A. McRae and C.E. Coleman published in Journal of Nuclear Materials 568 (2022) 1538	29
Stability of 〈100〉 dislocations formed in W	28
Inelastic collision effects of high-energy neutrons in tungsten materials	28
Editorial Board	28
A laboratory-scale process for producing dilithium beryllium tetrafluoride (FLiBe) with dissolved uranium tetrafluoride	27
Editorial Board	27
Evaluation of several conditioning matrices for the management of radioactive metal beryllium wastes	27
Microstructural analysis of tristructural isotropic particles in high-temperature steam mixed gas atmospheres	27
Micro-cantilever beam experiments and modeling in porous polycrystalline UO2	26
Anisotropy in the elasticity of α-U from first-principles calculations and nanoindentation	26
A novel type of core-shell structured secondary phase particles in Ge-addition modified Zircaloy-4 alloy subjected to β-phase region solution treatment	26
X-ray diffraction line profile analysis of defects in neutron-irradiated austenitic stainless steels at low displacement damage levels	26
Behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions	26
Critical comment to Letter to the Editor of G.A. McRae and C.E. Coleman published in Journal of Nuclear Materials 556 (2021) 153169	25
Editorial Board	25
Investigation of γ-	25
Analytical models for predicting the behavior of the Fukushima fuel debris during laboratory tests and long-term storage	25
Editorial Board	25
Modelling of defective CANDU fuel phenomena	24
First principles calculations of cohesive energy of fission-product-segregated grain boundary of UO2	24
The microstructure effects on irradiation response of ferritic – martensitic steels	24
Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel	24
Improved doping and densification of uranium oxide microspheres using starch as pore former	24
Triple ion beam irradiation of glass-ceramic materials for nuclear fusion technology	24
A fusion relevant data-driven engineering void swelling model for 9Cr tempered martensitic steels	24
Oriented intra-granular bubble transport due to coupling of pinned bubble growth and dislocation climb	24
Editorial Board	24
Editorial Board	24
Diffusion controlled hydrolysis in geopolymers under gamma irradiation	24
Interface evolution and corrosion performance of (TiTaNbZrNi)N HEA coatings with a hybrid architecture under 6 MeV Au-ion irradiation	23
Effect of prior microstructure on carbide precipitation in a Cr-Mo-V pressure vessel steel at 650 °C	23
Influence of point defect accumulation on in-pile thermal conductivity degradation: Fuel rod defect distribution and deviation between in-pile and post irradiation thermal conductivity	23
Equation of state for helium-xenon gas mixture studied by molecular dynamics simulations	23
Fast densification of dense nano-grained Gd2Zr2O7 ceramic prepared by two-step microwave sintering	23
Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten	23

Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2	23
Towards understanding the mechanism of titanium suppressing vacancy clustering/void nucleation in vanadium alloy	22
Numerical simulation of deuterium retention in tungsten under ELM-like conditions	22
No ball milling needed: Alternative ODS steel manufacturing with gas atomization reaction synthesis (GARS) and friction-based processing	22
A high-entropy alloy nitride protective coating for fuel cladding in high temperature lead-bismuth eutectic alloy	22
Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: Kinetics transition and failure mechanism of Cr coatings	22
Effect of aging and α’ segregation on oxidation and electrochemical behavior of FeCrAl alloys	22
Zirconium based neutron absorption material with outstanding corrosion resistance and mechanical properties	22
Evolution of IFMIF-DONES' heart: System overview of the Test Cell	22
Dose and dose rate dependence of precipitation in a series of surveillance RPV steels under ion and neutron irradiation	22
Glass-bonded ceramic waste forms for immobilization of radioiodine from caustic scrubber wastes	22
Effect of oxygen concentrations on the corrosion behavior of a duplex-phase FeNiCrCuAl high entropy alloy in supercritical water	22
Ab initio molecular dynamics (AIMD) simulations of NaCl, UCl3 and	21
Multi-objective optimization design of TRISO-based fully ceramic microencapsulated fuel	21
A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes	21
Helium bubbles diffusion in aluminum: Influence of gas pressure	21
Atomistic simulations of He bubbles in Beryllium	21
Weldability of irradiated Stainless Steel 304 materials harvested from the National Research Universal (NRU) reactor	21
Decontamination and solidification treatment on spent liquid scintillation cocktail	21
Improving hydrogen isotope permeation resistance of (TiVAlCrZr)O multi-component metal oxide coating by O+ Ion implantation	21
Cluster dynamics modeling of Mn-Ni-Si precipitates coupled with radiation-induced segregation in low-Cu reactor pressure vessel steels	21
A comprehensive review on decontamination of irradiated graphite waste	21
Cluster dynamics simulation of Zr hydrides formation on grain boundaries in Zr	20
Radiation-induced segregation at grain boundaries of alloy 800H: Experimentally-informed atomistic simulations	20
Effect of different Y components on optimization of dispersive Y2O3 particles in ODS-Cu	20
Study of the volatilization of cesium and rhenium in the waste vitrification process	20
Ion-irradiation-induced clustering in Fe-Mn-Ni-(Si) steels: Nucleation, growth and chemistry evolution	20
Atomistic simulation of α-Fe(100)-lead-bismuth eutectic (LBE) solid-liquid interface	20
Computational insights into the lattice dynamics of Pu(IV) oxalates	19
Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel	19
Vacancy accumulation mechanism at iron grain boundaries: The influence of grain boundary character and its coupling with grain size	19
Characterization of Li-rich Li2TiO3 ceramic pebbles prepared by rolling method sintered in air and vacuum	19
Radial hydride fraction with various rod internal pressures and hydrogen contents for Zr-Nb alloy cladding tube	19
Effect of Re aggregation doping configurations on the thermal and mechanical properties of W-Re alloys: A molecular dynamics study	19
Effects of Zr and/or Ti addition on the morphology, crystal and metal/oxide interface structures of nanoparticles in FeCrAl-ODS steels	19
Reply to S. Wang's comments (Journal of Nuclear Materials 570 (2022) 153952) on short communication of G.A. McRae and C.E. Coleman published in Journal of Nuclear Materials 568 (2022) 153889	19
Uniform oxidation in steam and nodular corrosion in gas phase of Zr-2.5Nb pressure tube material - effect of nature of initial oxide	19
Development of an image analysis code for hydrided Zircaloy using Dijkstra's algorithm and sensitivity analysis of radial hydride continuous path	19
A novel protocol to recycle zirconium from zirconium alloy cladding from used nuclear fuel rods	19
Radiation damage accumulation mechanisms at iron grain boundaries revealed by coupled atomic and coarse-grained simulations via the parameter-passing and structural feedback	19
Editorial Board	19
Formation of helical dislocations mediated by interstitials in ion irradiated FeCrAl alloy	19
Investigation of neutron irradiated W/CuCrZr joints	18
Evaluation of the thermal conductivity of chromium coatings for accident tolerant fuels using thermoreflectance techniques	18
Enhancement of oxidation resistance of Cr/CrN composite coating on Zr-4 surface by high lattice-matched interfacial Engineering	18
Effect of surface state of austenitic type 304L SS on oxide characteristics formed in high temperature high pressure water	18
Towards atomistic modelling of solid Pb-O formation and dissolution in liquid lead coolant: Interatomic potential development	18
Effect of scratch depth on high cycle fatigue behavior of Alloy 690TT stream generator tube	18
Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models	18
Hydrogen-enhanced oxidation of ferrite phase in stainless steel cladding and the contribution to stress corrosion cracking in deaerated high temperature water	18
An application of the DEM-FFT method to predict the thermal conductivity of high burnup fragmented fuel	18
Corrigendum to “Thermal corrosion behavior of Inconel 693, Hastelloy N and 310S in ceramic waste forming reactions” [J. Nucl. Mater. 603(2025)155416]	18
Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel	18
Defect evolution under intense electronic energy deposition in uranium dioxide	18
Incipient corrosion of FeCrAl alloys in H3BO3- and LiOH-containing pure water at 360 °C and 18.5 MPa	18
Dislocation loop coarsening and shape evolution upon annealing neutron-irradiated RAFM steel	18
A new interatomic potential of W-Ni-Fe systems for point defects and mechanical property studies	18
Improved approaches for small punch test to estimate the yield and ultimate tensile strength of metallic materials	18
Determining reference standard strength for neutron-irradiated reduced activation ferritic/martensitic steel F82H by Bayesian method	18
The effect of sample thickness on micro-mesoscale tensile properties of 304SS, HT-9, and CuCrZr	18
Interaction between an edge dislocation and faceted voids in body-centered cubic Fe	18
Raman spectroscopy of uranium nitride kernels	18
Molecular dynamics studies of helium bubble effects on grain boundary fracture vulnerabilities in an Fe70Ni11Cr19–1%H austenitic stainless steel	18
Characteristics of oxide-dispersion strengthened alloys produced by high-temperature severe deformation	18
Development of GD-containing austenitic stainless steel	18
Nano-micrometer scale characterization of PWSCC crack tips in the transition zone of 52M overlay and the implication to intergranular cracking	17
Highly efficient energy and mass transfer in bcc metals by supersonic 2-crowdions	17
Editorial Board	17
Modeling of the thermomechanical behavior of braided SiCf/SiC composite cladding tube during irradiation	17
Microstructural evolution of the Cr/FeCrAl coated Zircaloy-4 under simulated PWR and high-temperature steam oxidation environments	17
Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation	17
Improvement in the hydrothermal corrosion resistance of Ti-based nitride coatings by adding Cr for accident tolerant fuel cladding applications	17
He irradiation resistance performance in CrNiCo, CrFeNiCo, and CrFeMnNiCo multi-principal element alloys	17
Exploring the longevity of geopolymer waste forms co-hosting cationic and anionic radionuclides: A mechanistic investigation	17
Impact of the microstructure on the swelling of aluminum alloys: Characterization and modelling bases	17
Mechanical and high-temperature steam oxidation properties of Cr coatings deposited via high-power impulse magnetron sputtering	17
On the theory of the nucleation of gas bubbles at grain boundaries and incoherent inclusions	17
Statistical fracture behavior of doped UO2 using a ball-on-ring equibiaxial flexure test method	17
Simulation of uranium mononitride spent fuel: A thermodynamic approach	16
Experimental investigation and constitutive material modelling of low cycle fatigue of EUROFER97 for fusion applications	16

On the stable/metastable nature of the γ-hydride phase in Zircaloy-2: Microstructural characterization by electron diffraction, electron energy-loss spectroscopy, and diffraction line profile analysis	16
Helium migration in Zr-Nb multilayers under electric field	16
First-principles investigation of the thermophysical properties of NaCl, PuCl3, and NaCl-PuCl3 Molten salts	16
Shock response of He bubble in single crystal tungsten: molecular dynamics simulation study	16
Formation and stability of the early stage solute and defect clusters in Cu-free ferritic steels during irradiation	16
Characterizing accelerated precipitation in proton irradiated steel	16
Effect of hydrogen gas and leaching solution on the fast release of fission products from two PWR fuels	16
First-principles analysis of intergranular fracture in UN by Σ5(210) grain boundary segregated Xe and vacancy	16
Integrated simulation of U-10Mo monolithic fuel swelling behavior	16
Corrigendum to ‘Modeling injected interstitial effects on void swelling in self-ion irradiation experiments’ [Journal of Nuclear Materials 471 (2016) 200 – 207]	16
Controlled current-rate AC flash sintering of uranium dioxide	16
Predicting zeolites’ stability during the corrosion of nuclear waste immobilization glasses: Comparison with glass corrosion experiments	16
Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations	16
Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln	16
The incorporation of xenon at point defects and bubbles in uranium mononitride	16
Suppression of helium migration in arc-melted and 3D-printed CoCrFeMnNi high entropy alloy	16
Post-irradiation annealing of neutron-irradiated EUROFER97	16
Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide	16
Development of geopolymer based sacrificial materials for GEN IV severe accident mitigation	16
Manufacturing porous U-10Zr metallic fuels with controllable microstructure by volume control spark plasma sintering	16
Dynamic behavior of helium bubbles in Fe9Cr1.5W0.4Si F/M steel at elevated temperature	16
Additive manufacturing technologies for EUROFER97 components	16
Assessing Li accommodation at amorphous ZrO2 grain boundaries	16
Helium ion irradiation-induced damage of powder metallurgy-hot isostatic pressed Ni-based alloy GH3535 for molten salt reactor applications	16
The infiltration behavior and chemical compatibility of molten lead-bismuth eutectic in nuclear graphite at elevated temperature	16
Athermal evolution of nanocrystalline tungsten driven by irradiation	16
Effect of Irradiation on Ni-Inconel/Incoloy Heterostructures in Multimetallic Layered Composites	16
Understanding radiation effects in friction stir welded MA956 using ion irradiation and a rate theory model	15
Highly stable nanocrystalline oxide dispersion strengthened alloys with outstanding helium bubble suppression	15
Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation	15
Postirradiation characterization of palladium as an additive for fuel cladding chemical interaction mitigation in metallic fuel	15
He nanobubble driven W surface growth during low-energy He ion irradiations	15
The effects of Ti content and quenching on phase transformations, microstructures, and mechanical properties in uranium-titanium alloys	15
Accelerated statistical failure analysis of multifidelity TRISO fuel models	15
Dose and compositional dependence of irradiation-induced property change in FeCr	15
Insight into the interfacial microstructure and chemistry of hot isostatically pressed AA6061-AA6061 bonds for U-10Mo fuel cladding application	15
Prior implantation of hydrogen as a mechanism to delay helium bubbles, blistering, and exfoliation in titanium	15
Monitoring the gradual change in oxidation state during surface oxidation or reduction of uranium oxides by photoemission spectroscopy of the 5f states	15
A linked-scale coupled model of mass erosion and redistribution in plasma-exposed micro-foam surfaces	15
Experimental and numerical study on multiaxial creep behavior of 16MND5 steel at 700℃	15
Characterization and ion-irradiation studies of typical microstructures in nuclear graphite	15
MD simulation of interactions of atomic displacement cascades with β-Nb precipitates in a zirconium matrix	15
Predictions of the full-life pressurised water stress corrosion cracking behaviour of 690 weld joints	15
Microstructure evolution of magnetite layer on CLAM steel exposed to lead-bismuth eutectic containing 10−6 wt% oxygen at 500 °C	15
Lithium/titanium ratio: A key factor on crystal structure and mechanical properties of lithium titanate pebbles for tritium breeder	15
In-situ ion irradiation study of alloy 709 stainless steels with different processing histories	15
Proton irradiation effects in Molybdenum-Carbide-Graphite composites	15
Metallothermic reduction of Cerium Chloride in molten Salt using Li, Na, and Ca Metal	15
Modeling fission gas release at the mesoscale using multiscale DenseNet regression with attention mechanism and inception blocks	15
Degradation behavior of chromium-coated zirconium cladding under 1200 oC steam oxidation according to the coating microstructure	15
Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium	15
Hydrogen isotope permeation and retention behavior in the RAFM steel manufactured by laser powder bed fusion	15
Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment	15
Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing	15
Defects evolution induced by Fe and He ions irradiation in Ti3AlC2	15
A combined rate theory-population balance model of the evolution of irradiation-induced helium bubbles in metals during annealing	14
Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800 °C	14
Effect of temperature on apparent crack arrest toughness of Eurofer97 measured by a newly developed small specimen test technique	14
Demonstration of an integrated-heating load frame for quantitatively assessing microscale tensile properties of copper and Zircaloy-2	14
Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation	14
Pore structure development of oxidized nuclear graphite	14
A comprehensive study on the phase composition, mechanical properties and stability of Li4SiO4-Li2ZrO3 biphasic ceramics	14
Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes	14
Effect of multiple Ti doping on helium behavior in ZrCo	14
Effect of composition on the corrosion behavior of 24 statistically-designed alkali-borosilicate waste glasses	14
Plasticity improvement and radiation hardening reduction of Y doped V-4Cr-4Ti alloy	14
Tensile fracture behavior and texture evolution of a hot-rolled W–Y2(Zr)O3 alloy	14
Investigation of ion irradiation effects on mineral analogues of concrete aggregates	14
Determining the diffusion behavior of point defects in zirconium by a multiscale modelling approach	14
Phase decomposition of oxide film of flow accelerated corroded F82H steel under high-temperature iron irradiation	14
Micromechanical modeling of single crystal and polycrystalline UO2 at elevated temperatures	14
Voltammetry measurements in lithium chloride-lithium oxide (LiCl–Li2O) salt: An evaluation of working electrode materials	14
Nanopore graphene-tungsten composite with enhanced irradiated helium atoms storage capacity	14
Short communication: The effects of ageing and storage environment on the oxidation response of uranium nitride (UN) powders	14
Interaction of krypton and xenon with sodium and activated charcoal: Identification and modeling using gas chromatography and density functional theory	14
Mesoscale modeling of the effects of accelerated burnup on UO2 microstructural evolution	14
Thermal ratcheting of uranium simulated with a thermo-elasto-visco-plastic self-consistent polycrystal model	14
Low cycle fatigue of EUROFER97 investigated for test blanket modules of ITER: An interlaboratory study	14
On the influence of microstructure on the neutron irradiation response of HIPed SA508 steel for nuclear applications	14
Tungsten fiber-reinforced tungsten composites and their thermal stability	14
Effect of temperature on the fretting wear behavior of Cr-coated Zircaloy cladding in high-temperature pressurized water	14
KCl-UCl3 molten salts investigated by Ab Initio Molecular Dynamics (AIMD) simulations: A comparative study with three dispersion models	13
Hydrogen embrittlement of bulk W-0.5 wt% ZrC alloy induced by annealing in hydrogen atmosphere	13
Evolution of δ ferrite in a CF3 cast stainless steel upon neutron irradiation to 3, 5, 10, 20, and 40 dpa	13
Investigation on the failure mechanistic evolution of fretting corrosion of Alloy 690 with increasing cycles in high-temperature water	13
Chloride-induced stress corrosion cracking in Austenitic steels for SNF storage canisters - Recent understanding and advances in mitigation and repair	13
On the interactions of interstitial helium atom with helium bubble in tungsten: A molecular dynamics study	13
A first-principles study on the early-stage corrosion of a NiWNb alloy in a chloride salt environment	13
Deuterium transport and retention properties of representative fusion blanket structural materials	13
Uranium–plutonium–oxygen phase diagram: Investigating the solvus of fluorite's exsolution	13
The dynamic response of He bubble in bicrystal copper under uniaxial compression and tension	13
Effect of ultrasonic impact peening on stress corrosion cracking resistance of austenitic stainless-steel welds for nuclear canister applications	13
Radiation-induced effects in self-passivating W-Cr-Y alloy	13
Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment	13
Influence of Ni-Mn contents on the embrittlement of PWR RPV model steels irradiated to high fluences relevant for LTO beyond 60 years	13