Journal of Nuclear Materials

Article	Citations
High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment	84
The role of TeO2 insertion on the radiation shielding, structural and physical properties of borosilicate glasses	80
Additive manufacturing of silicon carbide for nuclear applications	57
Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan	57
Lead-bismuth eutectic (LBE) corrosion behavior of AlTiN coatings at 550 and 600゜C	55
A review of the LIBS analysis for the plasma-facing components diagnostics	53
Cr-coated Zr-4 alloy prepared by electroplating and its in situ He+ irradiation behavior	52
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding	51
Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4	48
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan	44
A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications	44
Efficient capture of radioactive iodine by a new bismuth-decorated electrospinning carbon nanofiber	43
Highly effective prussian blue-coated MXene aerogel spheres for selective removal of cesium ions	42
TRISO particle fuel performance and failure analysis with BISON	41
Design considerations for high entropy alloys in advanced nuclear applications	40
Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility	40
Perspectives on multiscale modelling and experiments to accelerate materials development for fusion	39
Review of manufacturing technologies for coated accident tolerant fuel cladding	39
High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage	37
Cold spray deposition of 304L stainless steel to mitigate chloride-induced stress corrosion cracking in canisters for used nuclear fuel storage	37
Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation	35
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign	35
The structure of molten FLiNaK	35
Thermal aging behaviors of duplex stainless steels used in nuclear power plant: A review	35
Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: Uranium mononitride	35

A study of the oxidation behaviour of FeCrAl-ODS in air and steam environments up to 1400 °C	35
Fracture-mechanical properties of neutron irradiated ITER specification tungsten	34
Fabrication of yttrium hydride for high-temperature moderator application	32
Processing of tungsten through electron beam melting	32
Cluster dynamics simulation of xenon diffusion during irradiation in UO2	32
Fission gas diffusion and release for Cr2O32
Molecular dynamics simulations of high-dose damage production and defect evolution in tungsten	32
Impact of neutron irradiation on the strength and ductility of pure and ZrC reinforced tungsten grades	31
Crystalline phosphates for HLW immobilization - composition, structure, properties and production of ceramics. Spark Plasma Sintering as a promising sintering technology	31
Ferrite formation and its effect on deformation mechanism of wire arc additive manufactured 308 L stainless steel	30
Correlation of microstructural and mechanical properties of neutron irradiated EUROFER97 steel	30
STEM Characterization of Dislocation Loops in Irradiated FCC Alloys	30
Revealing the synergistic effects of sequential and simultaneous dual beam irradiations in tungsten via in-situ TEM	29
A threshold density of helium bubbles induces a ductile-to-brittle transition at a grain boundary in nickel	29
U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels	29
Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy	28
Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors	28
A refined oxidation mechanism proposed for ferritic-martensitic steels exposed to oxygen-saturated liquid lead-bismuth eutectic at 400°C for 500 h	28
α-U and ω-UZr2 in neutron irradiated U-10Zr annular metallic fuel	28
Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding	28
Effect of brazing temperature, filler thickness and post brazing heat treatment on the microstructure and mechanical properties of W-Eurofer joints brazed with Cu interlayers	28
Helium bubble formation in refractory single-phase concentrated solid solution alloys under MeV He ion irradiation	27
Recrystallization at high temperature of two tungsten materials complying with the ITER specifications	27
Effect of Ce4+-substitution at A and B sites of Nd2Zr2O7: A study for plutonium incorporation in pyrochlores	27
Development of CuCrZr via Electron Beam Powder Bed Fusion (EB-PBF)	26
Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions	26
A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions	26
Design and strategy for next-generation silicon carbide composites for nuclear energy	26
A systematic investigation of the phase assemblage and microstructure of the zirconolite CaZr1-xCexTi2O7 system	26
Helium-induced damage behavior in high temperature nickel-based alloys with different chemical composition	25
Effect of helium bubbles on irradiation hardening of additive manufacturing 316L stainless steel under high temperature He ions irradiation	25
Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water	25
Visualization of hydrogen isotope distribution in yttrium and cobalt doped barium zirconates	25
Correlation between microstructure and mechanical properties in the age-hardenable Cu-Cr-Zr alloy	25
Protection of graphite from salt and gas permeation in molten salt reactors	25
Impact of microstructural properties on hardness of tungsten heavy alloy evaluated by stand-off LIBS after PSI plasma irradiation	25
Creep behavior of 316 L stainless steel manufactured by laser powder bed fusion	24
Using external ion irradiations for simulating self-irradiation damage in nuclear waste glasses: State of the art, recommendations and, prospects	24
Tensile properties and microstructure of additively manufactured Grade 91 steel for nuclear applications	24
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 °C in steam	24
Raman spectroscopy coupled to principal component analysis for studying UO2 nuclear fuels with different grain sizes due to the chromia addition	24
Electronic stopping in molecular dynamics simulations of cascades in 3C–SiC	24
Recent progress on preparation routes and performance evaluation of ODS/CDS-W alloys for plasma facing materials in fusion devices	24
On the irradiation tolerance of nano-grained Ni–Mo–Cr alloy: 1 MeV He+ irradiation experiment	24
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing	23
Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3–Li4SiO4 biphasic ceramic pebbles	23
DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions	23
B2O3-assisted low-temperature crystallization of pollucite structures and their potential applications in Cs+ immobilization	23
Radiation effects on structure and mechanical properties of borosilicate glasses	23
Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys	23

Architecture and properties of TCR fuel form	23
Results of the QUENCH-LOCA experimental program at KIT	23
First steps toward predicting corrosion behavior of structural materials in molten salts	22
Effects of carbon doping on irradiation resistance of Fe38Mn40Ni11Al4Cr7 high entropy alloys	22
The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys	22
Neutron irradiation tolerance of potassium-doped and rhenium-alloyed tungsten	22
Heavy-ion irradiation effects of Gd2Zr2O7 nanocrystalline ceramics as nuclear waste immobilization matrix	22
Thermal annealing and transformation of dimer F centers in neutron-irradiated Al2O3 single crystals	22
Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties	21
Charge compensation mechanisms in Nd-doped UO2 samples for stoichiometric and hypo-stoichiometric conditions: Lack of miscibility gap	21
Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments	21
Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis	21
Oxidation properties and microstructure of a chromium coating on zircaloy-4 fuel cladding material applied by atmospheric plasma spraying	21
Structural and compositional effects on the electronic excitation induced phase transformations in Gd2Ti2-yZryO7 pyrochlore	21
Semi-integral LOCA test of cold-spray chromium coated zircaloy-4 accident tolerant fuel cladding	21
Dislocation loop evolution and radiation hardening in nickel-based concentrated solid solution alloys	21
Irradiation effects on Al0.3CoCrFeNi and CoCrMnFeNi high-entropy alloys, and 316H stainless steel at 500 °C	21
High temperature zirconium alloys for fusion energy	21
Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load	20
Estimation of reliable displacements-per-atom based on athermal-recombination-corrected model in radiation environments at nuclear fission, fusion, and accelerator facilities	20
Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation	20
Hydride embrittlement resistance of Zircaloy-4 and Zr-Nb alloy cladding tubes and its implications on spent fuel management	20
Ni coating on 316L stainless steel using cage plasma treatment: Feasibility and swelling studies	20
Large-scale potassium-doped tungsten alloy with superior recrystallization resistance, ductility and strength induced by potassium bubbles	20
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants	20
Post-decontamination treatment of MXene after adsorbing Cs from contaminated water with the enhanced thermal stability to form a stable radioactive waste matrix	20
A critical review of the microstructure of U–Mo fuels	20
Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT	20
Comparison of K-doped and pure cold-rolled tungsten sheets: Tensile properties and brittle-to-ductile transition temperatures	19
Positron annihilation spectroscopy study of vacancy-type defects in He implanted polycrystalline α-SiC	19
10B(n, α)7Li reaction-induced gas bubble formation in Al–B4C neutron absorber irradiated in spent nuclear fuel pool	19
Nano-hardening features in high-dose neutron irradiated Eurofer97 revealed by atom-probe tomography	19
Interfacial characterization of dissimilar-metals bonding between vanadium alloy and Hastelloy X alloy by explosive welding	19
Microstructure, oxidation and corrosion properties of FeCrAl coatings with low Al content prepared by magnetron sputtering for accident tolerant fuel cladding	19
Atomistic simulations to study the effect of helium nanobubble on the shear deformation of nickel crystal	19
Interatomic potentials and defect properties of Fe–Cr–Al alloys	19
Investigation of the irradiation effects in additively manufactured 316L steel resulting in decreased irradiation assisted stress corrosion cracking susceptibility	19
Effect of stacking fault energy on damage microstructure in ion-irradiated CoCrFeNiMn concentrated solid solution alloys	19
The application of synchrotron micro-computed tomography to characterize the three-dimensional microstructure in irradiated nuclear fuel	19
Microstructural and crystallographic analysis of hydride reorientation in a zirconium alloy cladding tube	19
Significant suppression of void swelling and irradiation hardening in a nanograined/nanoprecipitated 14YWT-ODS steel irradiated by helium ions	19
Characterization of as-deposited cold sprayed Cr-coating on Optimized ZIRLO™ claddings	19
Gamma irradiation-induced defects in borosilicate glasses for high-level radioactive waste immobilisation	19
Study of radiation-induced amorphization of M23C6 in RAFM steels under iron irradiations	18
Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding	18
Application of machine learning in understanding the irradiation damage mechanism of high-entropy materials	18
Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten	18
Effects of dissolved oxygen on partial slip fretting corrosion of Alloy 690TT in high temperature pure water	18
Iodosodalite synthesis with hot isostatic pressing of precursors produced from aqueous and hydrothermal processes	18
High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)	18
Probing the Short-Range Ordering of Ion Irradiated Gd2Ti2-yZryO7 (0.0 ≤ y ≤ 2.0) Pyrochlore under Electronic Stopping Regime	18
Modeling fission product diffusion in TRISO fuel particles with BISON	18
Qualification pathways for additively manufactured components for nuclear applications	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
High temperature steam oxidation dynamics of U3Si2 with alloying additions: Al, Cr, and Y	18
Accelerated/reduced growth of tungsten fuzz by deposition of metals	18
Microstructural evolution of Mo-UO2 cermets under high temperature hydrogen environments	18
Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures	18
Irradiation effects on the fracture properties of UO2 fuels studied by micro-mechanical testing	18
Dynamic evolution of He bubble and its effects on void nucleation-growth and thermomechanical properties in the spallation of aluminum	17
Microstructural evolution of Cr-coated Zr-4 alloy prepared by multi-arc ion plating during high temperature oxidation	17
Characterisation of open volume defects in Fe–Cr and ODS Fe–Cr alloys after He+ and Fe+ ion irradiations	17
Characterizing microstructural evolution and low cycle fatigue behavior of 316H austenitic steel at high-temperatures	17
Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications	17
Solid sorbents for gaseous iodine capture and their conversion into stable waste forms	17
Fuel-cladding chemical interaction of a prototype annular U-10Zr fuel with Fe-12Cr ferritic/martensitic HT-9 cladding	17
Effects of TiC nanoparticle additions on microstructure and mechanical properties of FeCrAl alloys prepared by directed energy deposition	17
High spatial resolution thermal conductivity mapping of SiC/SiC composites	17
Spark plasma sintered tungsten – mechanical properties, irradiation effects and thermal shock performance	17
Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding	17
Helium ion irradiation enhanced precipitation and the impact on cavity formation in a HfNbZrTi refractory high entropy alloy	17
TEM characterization of dislocation loops in proton irradiated single crystal ThO2	17
Uranium carbide properties for advanced fuel modeling – A review	17
Effects of minor alloying addition on He bubble formation in the irradiated FeCoNiCr-based high-entropy alloys	17
Helium bubble nucleation in Laser Powder Bed Fusion processed 304L stainless steel	17
Interatomic potentials for irradiation-induced defects in iron	17
Molecular dynamics simulation of primary radiation damage in W-Ta alloys: Effect of tantalum	17
Hydrogen and its detection in fusion and fission nuclear materials – a review	17
Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases	17
The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC	17

Tungsten–tantalum alloys for fusion reactor applications	17
Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium	17
Raman and infrared spectra of plutonium (IV) oxalate and its thermal degradation products	16
Corrosion of 316H stainless steel in flowing FLiNaK salt	16
Study of thermodynamic properties of U1-yPuyO2 MOX fuel using classical molecular Monte Carlo simulations	16
In-situ TEM investigation of nano-scale helium bubble evolution in tantalum-doped tungsten at 800°C	16
UN microspheres embedded in UO2 matrix: An innovative accident tolerant fuel	16
Beyond U/Pu separation: Separation of americium from the highly active PUREX raffinate	16
Influence of Ni-Mn contents on the embrittlement of PWR RPV model steels irradiated to high fluences relevant for LTO beyond 60 years	16
Critical behavior of interfacial t-ZrO2 and other oxide features of zirconium alloy reaching critical transition condition	16
Tensile behavior of dual-phase titanium alloys under high-intensity proton beam exposure: Radiation-induced omega phase transformation in Ti-6Al-4V	16
Modeling W fuzz growth over polycrystalline W due to He ion irradiations at an elevated temperature	16
High-throughput ion irradiation of additively manufactured compositionally complex alloys	16
Effect of cyclic heat loading on pure tungsten for the ITER divertor	16
Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation	16
Heavy ion irradiation response of an additively manufactured 316LN stainless steel	16
Investigation of spatial relationship between helium bubbles and dislocation loops in RAFM steel	16
Post-LOCA ductility of Cr-coated cladding and its embrittlement limit	16
Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions	16
Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients	16
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation	16
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling	16
Benefit or harm of accident tolerant coatings on the low-cycle fatigue properties of Zr-4 cladding alloy: in-situ studies at 400°C	16
Phase-field simulations of intergranular fission gas bubble behavior in U3Si2 nuclear fuel	16
Strengthening mechanism of Nb addition in Fe–13Cr–4.5Al–2Mo alloys assessed by internal friction measurement	16
Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in Japan	16
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	16
Bubbles and precipitates formation and effects on the hardening of irradiated vanadium alloys	16
Mechanical properties of neutron-irradiated single crystal tungsten W(100) studied by indentation and FEM modelling	16
The kinetics of dynamic recrystallization and construction of constitutive modeling of RAFM steel in the hot deformation process	16
Primary radiation damage characteristics in displacement cascades of FeCrAl alloys	16
First-principles investigation of uranium mononitride (UN): Effect of magnetic ordering, spin-orbit interactions and exchange correlation functional	15
Microstructure evolution of hot-rolled pure and doped tungsten under various rolling reductions	15
Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel	15
Thermal and mechanical properties of U3Si2: A combined ab-initio and molecular dynamics study	15
The optical texture of PGA, Gilsocarbon, NBG-18, and IG-110 nuclear graphite	15
Deuterium retention in W and binary W alloys irradiated with high energy Fe ions	15
A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation	15
Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains	15
Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry	15
The dendrite growth, morphology control and deposition properties of uranium electrorefining	15
Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials	15
Implementation and Validation of the Hydride Nucleation-Growth-Dissolution (HNGD) model in BISON	15
Development of reduced activation ferritic/martensitic steels in China	15
Hydrothermal corrosion behavior of CVD SiC in high temperature water	15
On the long term estimation of hydrogen embrittlement risks of titanium for the fabrication of nuclear waste container in bentonite buffer of nuclear waste repository	15
Insight into interface cohesion and impurity-induced embrittlement in carbide dispersion strengthen tungsten from first principles	15
Fracture properties of an irradiated PWR UO2 fuel evaluated by micro-cantilever bending tests	15
Grain-boundary phosphorus segregation in highly neutron-irradiated reactor pressure vessel steels and its effect on irradiation embrittlement	15
Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions	15
Towards resolving a long existing phase stability controversy in the Zr-H, Ti-H systems	15
Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing	15
Recrystallization behaviour of high-flux hydrogen plasma exposed tungsten	15
Validating modern methods for impurity analysis in fluoride salts	15
Microwave-sintering preparation, phase evolution and chemical stability of Na1-2Sr Zr2(PO4)3 ceramics for immobilizing simulated radionuclides	15
Deuterium transport and retention properties of representative fusion blanket structural materials	15
A new heat capacity law for UO2, PuO2 and (U,Pu)O2 derived from molecular dynamics simulations and useable in fuel performance codes	15
A novel methodology for estimating tensile properties in a small punch test employing in-situ DIC based deflection mapping	15
Development of the Molten Salt Thermal Properties Database − Thermochemical (MSTDB−TC), example applications, and LiCl−RbCl and UF3−UF4 system assessments	14
Behaviour of magnesium phosphate cement-based materials under gamma and alpha irradiation	14
Performance of U3Si2 in an LWR following a cladding breach during normal operation	14
Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material	14
Effect of O/M ratio on sintering behavior of (Pu0.3U0.7)O2-x	14
Size-distribution of irradiation-induced dislocation-loops in materials used in the nuclear industry	14
Evolution of microstructure and texture of moderately warm-rolled pure tungsten during annealing at 1300 °C	14
A CALPHAD-informed approach to modeling constituent redistribution in Zr-based metallic fuels using BISON	14
Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel	14
Collapse of stacking fault tetrahedron and dislocation evolution in copper under shock compression	14
Mechanisms of plastic deformation and fracture of austenitic chromium-nickel steel irradiated during 45 years in WWER-440	14
Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals	14
Distinct He-induced damage evolution in nickel-based alloys irradiated at elevated temperatures	14
Electron backscattering coefficients of molybdenum and tungsten based on the Monte Carlo simulations	14
Uranium chemical species in LiCl-KCl eutectic under different conditions for the dissolution of U3O8	14
Design and fabrication of UN composites: From first principles to pellet production	14
Tritium release property of Li2TiO3-Li4SiO4 biphasic ceramics	14
Determining the acute oxidation behavior of several nuclear graphite grades	14
On the use of charged particles to characterize precipitation in irradiated reactor pressure vessel steels with a wide range of compositions	14
Investigating zirconium alloy corrosion with advanced experimental techniques: A review	14
Low leaching characteristics and encapsulation mechanism of Cs+ and Sr2+ from SAC matrix with radioactive IER	14
Short positron lifetime at vacancies observed in electron-irradiated tungsten: Experiments and first-principles calculations	14
Strontium ions capturing in aqueous media using exfoliated titanium aluminum carbide (Ti2AlC MAX phase)	14
Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation	14
TRANOX: Model for non-isothermal steam oxidation of zircaloy cladding	14
Radiation driven diffusion in γU-Mo	14
Nanobubbles diffusion in bcc uranium: Theory and atomistic modelling	14
Cold sprayed Cr-coating on Optimized ZIRLO™ claddings: the Cr/Zr interface and its microstructural and chemical evolution after autoclave corrosion testing	14
Embedded sensors in additively manufactured silicon carbide	14
Effect of inhomogeneous microstructure on the deformation and fracture mechanisms of 316LN stainless steel multi-pass weld joint using small punch test	14
Determining uranium ore concentrates and their calcination products via image classification of multiple magnifications	14
Irradiation resistance of chromium coatings for ATFC in the temperature range 300–550°C	14
Ab initio molecular dynamics (AIMD) simulations of NaCl, UCl3 and	14
Recent progress in experimental investigation of neutron irradiation response of tungsten	14
Optimization of the t/10 offset correlation method to obtain the yield strength with the Small Punch Test	14
Radiation damage buildup and basal vacancy cluster formation in hcp zirconium: A molecular dynamics study	14
Effect of cooling rate on the residual ductility of Post-LOCA Zircaloy-4 cladding	14