Journal of Nuclear Materials

Article	Citations
The role of TeO2 insertion on the radiation shielding, structural and physical properties of borosilicate glasses	109
High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment	106
Additive manufacturing of silicon carbide for nuclear applications	66
Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan	64
A review of the LIBS analysis for the plasma-facing components diagnostics	63
Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4	59
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan	52
Design considerations for high entropy alloys in advanced nuclear applications	50
Efficient capture of radioactive iodine by a new bismuth-decorated electrospinning carbon nanofiber	50
Thermal aging behaviors of duplex stainless steels used in nuclear power plant: A review	48
Review of manufacturing technologies for coated accident tolerant fuel cladding	48
High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage	47
Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation	44
Molecular dynamics simulations of high-dose damage production and defect evolution in tungsten	44
A study of the oxidation behaviour of FeCrAl-ODS in air and steam environments up to 1400 °C	44
TRISO particle fuel performance and failure analysis with BISON	44
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign	43
Perspectives on multiscale modelling and experiments to accelerate materials development for fusion	43
Crystalline phosphates for HLW immobilization - composition, structure, properties and production of ceramics. Spark Plasma Sintering as a promising sintering technology	42
Processing of tungsten through electron beam melting	40
STEM Characterization of Dislocation Loops in Irradiated FCC Alloys	39
Cluster dynamics simulation of xenon diffusion during irradiation in UO2	39
Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: Uranium mononitride	39
Fission gas diffusion and release for Cr2O37
High temperature zirconium alloys for fusion energy	36

Fracture-mechanical properties of neutron irradiated ITER specification tungsten	36
Ferrite formation and its effect on deformation mechanism of wire arc additive manufactured 308 L stainless steel	36
A refined oxidation mechanism proposed for ferritic-martensitic steels exposed to oxygen-saturated liquid lead-bismuth eutectic at 400°C for 500 h	35
Development of CuCrZr via Electron Beam Powder Bed Fusion (EB-PBF)	34
Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors	33
Helium bubble formation in refractory single-phase concentrated solid solution alloys under MeV He ion irradiation	32
Design and strategy for next-generation silicon carbide composites for nuclear energy	31
Correlation between microstructure and mechanical properties in the age-hardenable Cu-Cr-Zr alloy	30
Beyond U/Pu separation: Separation of americium from the highly active PUREX raffinate	30
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 °C in steam	30
α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel	30
Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions	30
Creep behavior of 316 L stainless steel manufactured by laser powder bed fusion	29
Recent progress on preparation routes and performance evaluation of ODS/CDS-W alloys for plasma facing materials in fusion devices	29
Recrystallization at high temperature of two tungsten materials complying with the ITER specifications	29
A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions	28
Architecture and properties of TCR fuel form	27
Effect of helium bubbles on irradiation hardening of additive manufacturing 316L stainless steel under high temperature He ions irradiation	27
Tensile properties and microstructure of additively manufactured Grade 91 steel for nuclear applications	27
Helium-induced damage behavior in high temperature nickel-based alloys with different chemical composition	27
Impact of microstructural properties on hardness of tungsten heavy alloy evaluated by stand-off LIBS after PSI plasma irradiation	27
Radiation effects on structure and mechanical properties of borosilicate glasses	26
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	26
Microstructural evolution of Cr-coated Zr-4 alloy prepared by multi-arc ion plating during high temperature oxidation	26
Effects of minor alloying addition on He bubble formation in the irradiated FeCoNiCr-based high-entropy alloys	26
On the irradiation tolerance of nano-grained Ni–Mo–Cr alloy: 1 MeV He+ irradiation experiment	26
B2O3-assisted low-temperature crystallization of pollucite structures and their potential applications in Cs+ immobilization	26
DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions	26
Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties	25
Effects of carbon doping on irradiation resistance of Fe38Mn40Ni11Al4Cr7 high entropy alloys	25
Electronic stopping in molecular dynamics simulations of cascades in 3C–SiC	25
First steps toward predicting corrosion behavior of structural materials in molten salts	25
Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding	25
Oxidation properties and microstructure of a chromium coating on zircaloy-4 fuel cladding material applied by atmospheric plasma spraying	24
Microstructure, oxidation and corrosion properties of FeCrAl coatings with low Al content prepared by magnetron sputtering for accident tolerant fuel cladding	24
Raman spectroscopy coupled to principal component analysis for studying UO2 nuclear fuels with different grain sizes due to the chromia addition	24
Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials	24
Post-decontamination treatment of MXene after adsorbing Cs from contaminated water with the enhanced thermal stability to form a stable radioactive waste matrix	23
Significant suppression of void swelling and irradiation hardening in a nanograined/nanoprecipitated 14YWT-ODS steel irradiated by helium ions	23
Characterization of as-deposited cold sprayed Cr-coating on Optimized ZIRLO™ claddings	23
Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten	23
Gamma irradiation-induced defects in borosilicate glasses for high-level radioactive waste immobilisation	23
Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments	23
Characterizing microstructural evolution and low cycle fatigue behavior of 316H austenitic steel at high-temperatures	23
Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis	23
Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys	23
Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in Japan	23
A critical review of the microstructure of U–Mo fuels	23
Large-scale potassium-doped tungsten alloy with superior recrystallization resistance, ductility and strength induced by potassium bubbles	23
Thermal annealing and transformation of dimer F centers in neutron-irradiated Al2O3 single crystals	23

Hydride embrittlement resistance of Zircaloy-4 and Zr-Nb alloy cladding tubes and its implications on spent fuel management	22
Probing the Short-Range Ordering of Ion Irradiated Gd2Ti2-yZryO7 (0.0 ≤ y ≤ 2.0) Pyrochlore under Electronic Stopping Regime	22
Comparison of K-doped and pure cold-rolled tungsten sheets: Tensile properties and brittle-to-ductile transition temperatures	22
Qualification pathways for additively manufactured components for nuclear applications	22
Application of machine learning in understanding the irradiation damage mechanism of high-entropy materials	22
Atomistic simulations to study the effect of helium nanobubble on the shear deformation of nickel crystal	22
Ni coating on 316L stainless steel using cage plasma treatment: Feasibility and swelling studies	22
Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load	21
High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)	21
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants	21
Recent progress in experimental investigation of neutron irradiation response of tungsten	21
Primary radiation damage characteristics in displacement cascades of FeCrAl alloys	21
Cold sprayed Cr-coating on Optimized ZIRLO™ claddings: the Cr/Zr interface and its microstructural and chemical evolution after autoclave corrosion testing	21
Effect of stacking fault energy on damage microstructure in ion-irradiated CoCrFeNiMn concentrated solid solution alloys	21
Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures	21
Modeling fission product diffusion in TRISO fuel particles with BISON	21
Effect of Li metal addition on corrosion control of Hastelloy N and stainless steel 316H in molten LiF-NaF-KF	21
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling	21
The dendrite growth, morphology control and deposition properties of uranium electrorefining	20
Development of the Molten Salt Thermal Properties Database − Thermochemical (MSTDB−TC), example applications, and LiCl−RbCl and UF3−UF4 system assessments	20
Interatomic potentials and defect properties of Fe–Cr–Al alloys	20
Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases	20
Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding	20
Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT	20
Post-LOCA ductility of Cr-coated cladding and its embrittlement limit	20
Molecular dynamics simulation of primary radiation damage in W-Ta alloys: Effect of tantalum	20
Corrosion of 316H stainless steel in flowing FLiNaK salt	20
Development of reduced activation ferritic/martensitic steels in China	20
Uranium carbide properties for advanced fuel modeling – A review	20
Mechanical properties of neutron-irradiated single crystal tungsten W(100) studied by indentation and FEM modelling	20
Implementation and Validation of the Hydride Nucleation-Growth-Dissolution (HNGD) model in BISON	20
Phase-field simulations of intergranular fission gas bubble behavior in U3Si2 nuclear fuel	20
TEM characterization of dislocation loops in proton irradiated single crystal ThO2	20
Accelerated/reduced growth of tungsten fuzz by deposition of metals	20
Effects of pre-exposure and simulated corrosion “pits” on liquid metal embrittlement of T91 steel exposed to liquid lead-bismuth eutectic at 350 °C	19
Evaluation of thermophysical properties of the LiCl-KCl system via ab initio and experimental methods	19
Benefit or harm of accident tolerant coatings on the low-cycle fatigue properties of Zr-4 cladding alloy: in-situ studies at 400°C	19
Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility	19
Validating modern methods for impurity analysis in fluoride salts	19
Preparation and irradiation stability of A2B2O7 pyrochlore high-entropy ceramic for immobilization of high-level nuclear waste	19
Effects of TiC nanoparticle additions on microstructure and mechanical properties of FeCrAl alloys prepared by directed energy deposition	19
Dynamic evolution of He bubble and its effects on void nucleation-growth and thermomechanical properties in the spallation of aluminum	19
Effects of dissolved oxygen on partial slip fretting corrosion of Alloy 690TT in high temperature pure water	19
Raman and infrared spectra of plutonium (IV) oxalate and its thermal degradation products	19
Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature	19
Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding	19
Tensile behavior of dual-phase titanium alloys under high-intensity proton beam exposure: Radiation-induced omega phase transformation in Ti-6Al-4V	19
Effects of ultrasonic surface rolling processing on the corrosion properties of uranium metal	19
Effects of composition and microstructure on oxidation and stress corrosion cracking susceptibility of stainless steel claddings in hydrogenated PWR primary water	19
Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten	19
Helium ion irradiation enhanced precipitation and the impact on cavity formation in a HfNbZrTi refractory high entropy alloy	19
In-situ TEM investigation of nano-scale helium bubble evolution in tantalum-doped tungsten at 800°C	19
Tungsten–tantalum alloys for fusion reactor applications	19
Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium	19
UN microspheres embedded in UO2 matrix: An innovative accident tolerant fuel	18
High-throughput ion irradiation of additively manufactured compositionally complex alloys	18
Influence of the transient conditions on release of corrosion products and oxidation of alloy 690 tubes during pressurized water reactor restart after steam generators replacement	18
A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation	18
High spatial resolution thermal conductivity mapping of SiC/SiC composites	18
A new heat capacity law for UO2, PuO2 and (U,Pu)O2 derived from molecular dynamics simulations and useable in fuel performance codes	18
Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding	18
Galvanic corrosion study between low alloy steel A508 and 309/308 L stainless steel dissimilar metals: A case study of the effects of oxide film and exposure time	18
Bubbles and precipitates formation and effects on the hardening of irradiated vanadium alloys	18
Ab initio molecular dynamics (AIMD) simulations of NaCl, UCl3 and	18
Low leaching characteristics and encapsulation mechanism of Cs+ and Sr2+ from SAC matrix with radioactive IER	18
Characterization of Al/B4C composite materials fabricated by powder metallurgy process technique for nuclear applications	18
Hydrogen and its detection in fusion and fission nuclear materials – a review	18
Determining the acute oxidation behavior of several nuclear graphite grades	18
Solid sorbents for gaseous iodine capture and their conversion into stable waste forms	18
Cluster dynamics modeling of irradiation growth in single crystal Zr	18
Mechanical behavior of SiC/SiC composites reinforced with new Tyranno SA4 fibers: Effect of interphase thickness and comparison with Tyranno SA3 and Hi-Nicalon S reinforced composites	18
Heavy ion irradiation response of an additively manufactured 316LN stainless steel	17
Strontium ions capturing in aqueous media using exfoliated titanium aluminum carbide (Ti2AlC MAX phase)	17
Spark plasma sintered tungsten – mechanical properties, irradiation effects and thermal shock performance	17
Modeling W fuzz growth over polycrystalline W due to He ion irradiations at an elevated temperature	17
Experiments and modelling of multiple sequential MeV ion irradiations and deuterium exposures in tungsten	17
Strengthening mechanism of Nb addition in Fe–13Cr–4.5Al–2Mo alloys assessed by internal friction measurement	17
Thermodynamics of hydrogen in graphite at high temperature and the effects of oxidation, irradiation and isotopics	17
Microwave-sintering preparation, phase evolution and chemical stability of Na1-2Sr Zr2(PO4)3 ceramics for immobilizing simulated radionuclides	17
Influence of Ni-Mn contents on the embrittlement of PWR RPV model steels irradiated to high fluences relevant for LTO beyond 60 years	17

Ultra-fast adsorption of radioactive-U(VI) and Cs(I) with high adsorption capacity towards CAA@MgAlFe spongy-like aerogel: Mechanism and application feasibility study	17
Critical behavior of interfacial t-ZrO2 and other oxide features of zirconium alloy reaching critical transition condition	17
Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing	17
Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field	17
Effect of cyclic heat loading on pure tungsten for the ITER divertor	17
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	17
Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions	17
Dose rate effects on damage accumulation and void growth in self-ion irradiated tungsten	17
Progress in additive manufacturing of pure tungsten for plasma-facing component applications	17
Towards resolving a long existing phase stability controversy in the Zr-H, Ti-H systems	17
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation	17
Effect of He on the irradiation resistance of equiatomic CoCrFeMnNi high-entropy alloy	17
Embedded sensors in additively manufactured silicon carbide	17
Deuterium retention in W and binary W alloys irradiated with high energy Fe ions	17
The optical texture of PGA, Gilsocarbon, NBG-18, and IG-110 nuclear graphite	17
Irradiation resistance of chromium coatings for ATFC in the temperature range 300–550°C	17
Helium bubble nucleation in Laser Powder Bed Fusion processed 304L stainless steel	17
The kinetics of dynamic recrystallization and construction of constitutive modeling of RAFM steel in the hot deformation process	17
Dislocation dynamics simulation of thermal annealing of a dislocation loop microstructure	16
Investigation of spatial relationship between helium bubbles and dislocation loops in RAFM steel	16
Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry	16
Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains	16
Synergistic effects of Si and Y on corrosion behavior of cast cladding steels by pre-laying Y powder for nuclear applications in static liquid LBE	16
Distinct He-induced damage evolution in nickel-based alloys irradiated at elevated temperatures	16
Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation	16
Electron backscattering coefficients of molybdenum and tungsten based on the Monte Carlo simulations	16
Effect of purity on the vacancy defects induced in self–irradiated tungsten: A combination of PAS and TEM	16
Microstructure evolution and lead-bismuth eutectic corrosion behavior of 11Cr1Si ferritic/martensitic steel after proton irradiation	16
First-principles investigation of uranium mononitride (UN): Effect of magnetic ordering, spin-orbit interactions and exchange correlation functional	16
Diffusion, Trapping, and Dissociation Behaviours of Helium at the Σ5 Grain Boundary in Tungsten: A Molecular Dynamics Study	16
The stability of γ′ precipitates in a multi-component FeCoNiCrTi0.2 alloy under elevated-temperature irradiation	16
Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel	16
Short positron lifetime at vacancies observed in electron-irradiated tungsten: Experiments and first-principles calculations	16
Irradiation damages of structural materials under different irradiation environments	16
Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation	16
Oxidation behavior and microstructural evolution of Cr coatings prepared by multi-arc ion plating on Zry-4 in steam environments up to 1400 °C	16
Grain-boundary phosphorus segregation in highly neutron-irradiated reactor pressure vessel steels and its effect on irradiation embrittlement	16
Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation	16
Influence of neutron irradiation on Al-6061 alloy produced via ultrasonic additive manufacturing	16
TRANOX: Model for non-isothermal steam oxidation of zircaloy cladding	16
Effect of heat treatment on creep behavior of 316 L stainless steel manufactured by laser powder bed fusion	15
Recrystallization behaviour of high-flux hydrogen plasma exposed tungsten	15
Corrosion mechanism of lead-bismuth eutectic at grain boundary in ferritic steels and the effect of alloying elements: A first-principles study	15
Development and characterization of advanced neutron multiplier materials	15
Deuterium transport and retention properties of representative fusion blanket structural materials	15
Effect of stacking fault energy on irradiation damage in reduced activation high entropy alloys	15
LIBS study of ITER relevant tungsten–oxygen coatings exposed to deuterium plasma in Magnum-PSI	15
A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON	15
A micromechanical analysis of swelling-induced embrittlement in neutron-irradiated austenitic stainless steels	15
Radiation damage buildup and basal vacancy cluster formation in hcp zirconium: A molecular dynamics study	15
Effect of Ni, Mo and Mn content on spinodal decomposition kinetics and G-phase precipitation of aged model cast austenitic stainless steels	15
Behaviour of magnesium phosphate cement-based materials under gamma and alpha irradiation	15
Self-healing behavior of Cr-coated Zr alloy cladding in high temperature steam oxidation process	15
Development of new embrittlement trend curve based on Japanese surveillance and atom probe tomography data	15
Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering	15
Understanding why dislocation loops are visible in transmission electron microscopy: The tungsten case	15
Evolution of microstructure and texture of moderately warm-rolled pure tungsten during annealing at 1300 °C	15
Raman signatures from age-dating PuO2 since last calcination	15
Effect of Salt Composition and Microstructure on Stress Corrosion Cracking of 316L Austenitic Stainless Steel for Dry Storage Canisters	15
Swelling of U-Mo Monolithic Fuel: Developing a Predictive Swelling Correlation under Research Reactor Conditions	15
Thermal diffusivity of irradiated tungsten and tungsten-rhenium alloys	15
Technology readiness assessment of materials for DEMO in-vessel applications	15
Radiation driven diffusion in γU-Mo	15
Enhanced irradiation tolerance of Fe30Cr25Ni20Co15Mn10 high-entropy alloy via nanotwin boundaries	15
Dismantling nuclear waste rich in P2O5, MoO3 and ZrO2: How do these oxides incorporate in aluminoborosilicate glasses?	15
Deuterium retention and desorption behavior of W-Ta-Cr-V high entropy alloy	15
Recent trends in metallic fast reactor fuels research	15
Irradiation hardening of stainless steel model alloy after Fe-ion irradiation and post-irradiation annealing treatment	15
Effect of multiple Ti doping on helium behavior in ZrCo	15
Radiation-induced amorphization of M23C6 in F82H steel: An atomic-scale observation	15
Finnis–Sinclair-type potential for atomistic simulation of defects behaviour in V-Ti-Ta ternary system	15
Chemisorption, diffusion and permeation of hydrogen isotopes in bcc bulk cr and cr(100) surface: First-principles dft simulations	15
In-situ studies on the mechanical properties of He ion irradiated nanotwinned Ag	15
Thermomechanical characterisation of W-Eurofer 97 brazed joints	15
An ab-initio study of hydrogen trapping energetics at BCC tungsten metal-noble gas interfaces	15
Design and fabrication of UN composites: From first principles to pellet production	15
Uranium chemical species in LiCl-KCl eutectic under different conditions for the dissolution of U3O8	15
In-situ ion irradiation induced grain growth in nanocrystalline ceria	14
Size-distribution of irradiation-induced dislocation-loops in materials used in the nuclear industry	14
Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: Kinetics transition and failure mechanism of Cr coatings	14
Post-irradiation annealing of neutron-irradiated EUROFER97	14
Combined evaluation of Young modulus and fracture toughness in small specimens of fine grained nuclear graphite using 3D image analysis	14
Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data	14
Segregation and coalescence behavior of helium bubbles in tungsten	14
The effects of post-irradiation isochronous annealing on defects evolution and hardening in Hastelloy N alloy	14
The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts	14
Study on thermal stability and irradiation response of copper/iron nano-multilayer composite fabricated by cross accumulative roll bonding	14
Effect of radial hydride on delayed hydride cracking behaviour of Zr-2.5Nb pressure tube material	14
Iodine local environment in high pressure borosilicate glasses: An X-ray photoelectron spectroscopy and X-ray absorption spectroscopy investigation	14
Radiation-induced effects in neutron- and electron-irradiated lithium silicate ceramic breeder pebbles	14
Defect cluster and nonequilibrium gas bubble associated growth in irradiated UMo fuels – A cluster dynamics and phase field model	14
A high-entropy alloy nitride protective coating for fuel cladding in high temperature lead-bismuth eutectic alloy	14
Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440	14
Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel	14
The incorporation of Nd or Ce in CaZrTi2O7 zirconolite: Ceramic versus glass-ceramic	14