Journal of Nuclear Materials
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Void swelling in pure iron after sequential self-ion-irradiation at different energies: Effect of injected interstitials and additional damage in regions containing pre-existing voids.
598:155178-155178.
2024
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Formation and dissolution of carbides and precipitates in self-ion irradiated HT9 alloy.
588:154819-154819.
2024
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Evolution of dislocation loops and voids in post-irradiation annealed ThO2: A combined in-situ TEM and cluster dynamics investigation.
586:154686-154686.
2023
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The effect of secondary phases on microstructure and irradiation damage in an as-built additively manufactured 316 L stainless steel with a hafnium compositional gradient.
587:154708-154708.
2023
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Effect of the free surface on near-surface void swelling in self-ion irradiated single crystal pure iron considering the carbon effect.
585:154594-154594.
2023
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Ion irradiation study of lithium silicates for fusion blanket applications.
576:154281-154281.
2023
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Modeling injected interstitial effects on void swelling in self-ion irradiation experiments (vol 471, pg 200, 2016).
576:154253-154253.
2023
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Irradiation response of innovatively engineered metastable TRIP high entropy alloy.
574:154217-154217.
2023
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A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals.
573:154140-154140.
2023
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An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels.
574:154203-154203.
2022
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Orientation-selected micro-pillar compression of additively manufactured 316L stainless steels: Comparison of as-manufactured, annealed, and proton-irradiated variants.
566:153739-153739.
2022
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Experimentally validated multiphysics modeling of fracture induced by thermal shocks in sintered UO2 pellets.
565:153719-153719.
2022
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Behavior of helium cavities in ion-irradiated W-Ni-Fe ductile-phase toughened tungsten.
561:153565-153565.
2022
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Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium.
561:153519-153519.
2022
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Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking.
560:153493-153493.
2022
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TEM characterization of dislocation loops in proton irradiated single crystal ThO2.
552:152998-152998.
2021
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Heavy ion irradiation response of an additively manufactured 316LN stainless steel.
546:152745-152745.
2021
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Atom probe tomography characterization of high-dose ion irradiated MA957.
545:152528-152528.
2021
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Helium retention, bubble superlattice formation and surface blistering in helium-irradiated tungsten.
545:152722-152722.
2021
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Oxide dispersoid coherency of a ferritic-martensitic 12Cr oxide-dispersion-strengthened alloy under self-ion irradiation.
544:152671-152671.
2021
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Ni coating on 316L stainless steel using cage plasma treatment: Feasibility and swelling studies.
540:152385-152385.
2020
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Radiation response of FeCrAl-coated Zircaloy-4.
536:152175-152175.
2020
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Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy.
531:151982-151982.
2020
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Effect of laser welding on deformation mechanisms in irradiated austenitic stainless steel.
528:151878-151878.
2020
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Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels.
527:151818-151818.
2019
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Tribochemistry of inconel 617 during sliding contact at 950 degrees C under helium environment for nuclear reactors.
521:21-30.
2019
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Interface reactions and mechanical properties of FeCrAl-coated Zircaloy-4.
519:57-63.
2019
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Compositional effects on radiation tolerance of amorphous silicon oxycarbide.
518:241-246.
2019
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Strength and plasticity of amorphous silicon oxycarbide.
516:289-296.
2019
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Chemical imaging and diffusion of hydrogen and lithium in lithium aluminate.
511:1-10.
2018
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Dispersoid stability in ion irradiated oxide-dispersion-strengthened alloy.
509:504-512.
2018
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Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction.
497:10-15.
2017
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A preliminary investigation of high dose ion irradiation response of a lanthana-bearing nanostructured ferritic steel processed via spark plasma sintering.
495:78-84.
2017
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Nanostructural evolution and behavior of H and Li in ion-implanted -LiAlO2.
494:411-421.
2017
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Influence of laser shock peening on irradiation defects in austenitic stainless steels.
489:203-210.
2017
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Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions.
487:96-104.
2017
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Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations.
486:86-95.
2017
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A Monte Carlo simulation code for calculating damage and particle transport in solids: The case for electron-bombarded solids for electron energies up to 900 MeV.
485:98-104.
2017
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Radiation response of alloy T91 at damage levels up to 1000 peak dpa.
482:257-265.
2016
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Monte Carlo modeling of cavity imaging in pure iron using back scatter electron scanning microscopy.
480:420-428.
2016
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High temperature radiation responses of amorphous SiOC/crystalline Fe nanocomposite.
479:411-417.
2016
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Modeling injected interstitial effects on void swelling in self-ion irradiation experiments.
471:200-207.
2016
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Intermetallic formation and interdiffusion in diffusion couples made of uranium and single crystal iron.
467:82-88.
2015
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Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation.
467:42-49.
2015
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Measurements of the liquidus surface and solidus transitions of the NaCl-UCl3 and NaCl-UCl3-CeCl3 phase diagrams.
466:280-285.
2015
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The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450C.
465:343-348.
2015
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Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel.
462:191-204.
2015
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Superior radiation tolerant materials: Amorphous silicon oxycarbide.
461:200-205.
2015
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Radiation effects on interface reactions of U/Fe, U/(Fe plus Cr), and U/(Fe plus Cr plus Ni).
456:302-310.
2015
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The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 C.
465:343-348.
2015
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Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions.
453:176-181.
2014
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Measurement of thermal diffusivity of depleted uranium metal microspheres.
446:100-105.
2014
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Phase field simulation of grain growth in porous uranium dioxide.
446:90-99.
2014
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Phase transformations and defect clusters in single crystal SrTiO3 irradiated at different temperatures.
442:143-147.
2013
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Size-dependent radiation tolerance in ion irradiated TiN/AlN nanolayer films.
441:47-53.
2013
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Candidate molten salt investigation for an accelerator driven subcritical core.
440:298-303.
2013
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Comparisons of radiation damage in He ion and proton irradiated immiscible Ag/Ni nanolayers.
440:310-318.
2013
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Coexistence of the and phases in an as-cast uranium-rich UZr alloy.
436:100-104.
2013
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Enhanced ion irradiation tolerance properties in TiN/MgO nanolayer films.
434:217-222.
2013
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Understanding the phase equilibrium and irradiation effects in Fe-Zr diffusion couples.
432:205-211.
2013
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Radiation damage at the coherent anatase TiO2/SrTiO3 interface under Ne ion irradiation.
429:177-184.
2012
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Radiation damage in helium ion irradiated nanocrystalline Fe.
425:140-146.
2012
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Enhanced radiation tolerance of ultrafine grained Fe-Cr-Ni alloy.
420:235-240.
2012
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Helium bubble growth at BCC twist grain boundaries.
419:201-207.
2011
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Properties of Helium bubbles in Fe and FeCr alloys.
418:261-268.
2011
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Flow behaviour of autoclaved, 20% cold worked, Zr2.5Nb alloy pressure tube material in the temperature range of room temperature to 800C.
412:22-29.
2011
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The U-Ti system: Strengths and weaknesses of the CALPHAD method.
419:177-185.
2011
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Thermodynamic study of the Np-Zr system.
409:1-8.
2011
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Interface enabled defects reduction in helium ion irradiated Cu/V nanolayers.
407:178-188.
2010
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He ion irradiation damage in Fe/W nanolayer films.
389:233-238.
2009
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Size dependent enhancement of helium ion irradiation tolerance in sputtered Cu/V nanolaminates.
385:629-632.
2009
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Properties of plutonium and its alloys for use as fast reactor fuels.
383:112-118.
2008
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Amorphization of MgAl2O4 spinel using 1.5 MeV Xe+ ions under cryogenic irradiation conditions.
304:237-241.
2002
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Radiation damage effects in zirconia.
274:66-77.
1999
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Effects of ionizing radiation in ceramics.
253:113-119.
1998
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In situ observation of defect growth beyond the irradiated region in yttria-stabilized zirconia induced by 400 keV xenon ion-beam at 90 and 30C.
244:266-272.
1997
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Ion beam analysis of MgAl2O4 spinel irradiated with fast neutrons to 50250 dpa.
239:284-290.
1996
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Structure and mechanical properties of irradiated magnesium aluminate spinel.
232:59-64.
1996
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Cation disorder in high dose, neutron-irradiated spinel.
219:128-134.
1995
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DIFFUSION OF LI-6 ISOTOPES IN LITHIUM ALUMINATE CERAMICS USING NEUTRON DEPTH PROFILING.
203:43-49.
1993
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RADIATIVE HEAT-TRANSFER IN POROUS URANIUM-DIOXIDE.
202:87-97.
1993
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THE RESULTS OF POSTIRRADIATION EXAMINATIONS OF VVER-1000 AND VVER-440 FUEL-RODS.
178:306-311.
1991
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THERMOPHYSICAL PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY.
173:261-273.
1990
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TRANSPORT PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY.
173:274-283.
1990
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MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .2. MECHANICAL-PROPERTIES.
171:271-288.
1990
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MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .3. TRANSPORT-PROPERTIES.
171:289-299.
1990
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MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .4. THERMODYNAMIC PROPERTIES.
171:300-318.
1990
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PRELIMINARY INVESTIGATIONS OF THE SURFACE-CHEMISTRY OF TITANIUM GETTERING.
123:1151-1155.
1984
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Structures and properties of rapidly solidified 9Cr-lMo steel.
122:789-793.
1984
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A threshold density of helium bubbles induces a ductile -to -brittle transition at a grain boundary in nickel.
533:152118-152118.
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An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor.
441:473-486.
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Bismuth-embedded SBA-15 mesoporous silica for radioactive iodine capture and stable storage.
465:556-564.
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Effect of free surfaces on localized plastic deformation in single-crystal nickel containing helium bubbles and radiation-induced self-interstitial atom clusters.
587:154741-154741.
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Effect of grain boundaries and rigid inclusions on plasticity in nickel bicrystals containing helium bubbles and radiation-induced self-interstitial atom clusters.
594:155030-155030.
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Formation, migration, and clustering energies of interstitial He in -quartz and -cristobalite.
479:224-231.
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Glass composite waste forms for iodine confined in bismuth-embedded SBA-15.
480:150-158.
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He implantation of bulk CuNb nanocomposites fabricated by accumulated roll bonding.
452:57-60.
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Healing of nanocracks by collision cascades in nickel.
555:153124-153124.
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Irradiation-induced shift in the thermodynamic stability of phases and the self-healing effect in transformative high entropy alloys.
597:155093.
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Micro-pillar compression of proton-irradiated chromium examined using cross-sectional site selection, electron microscopy, and molecular dynamics simulation.
600:155299-155299.
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Microstructural and compositional evolutions in -LiAlO2 pellets during ion irradiation at an elevated temperature.
591:154925.
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Novel synthesis of bismuth-based adsorbents for the removal of 129I in off-gas.
457:1-8.
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Structure of KurdjumovSachs interfaces in simulations of a copperniobium bilayer.
372:45-52.
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The dependence on displacement rate and temperature of near-surface void-denuding in self-ion irradiated pure polycrystalline and single-crystal iron.
599:155262-155262.
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Vacancy and interstitial interactions with crystal/amorphous, metal/covalent interfaces.
539:152329-152329.
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Grain refinement of T91 alloy by equal channel angular pressing
2009
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Effect of severe ausforming via equal channel angular extrusion on the shape memory response of a NiTi alloy
2007
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