Journal of Nuclear Materials - Texas A&M University (TAMU) Scholar

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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. 2024
Formation and dissolution of carbides and precipitates in self-ion irradiated HT9 alloy. 588:154819-154819. 2024
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. 2023
Evolution of dislocation loops and voids in post-irradiation annealed ThO₂: A combined in-situ TEM and cluster dynamics investigation. 586:154686-154686. 2023
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
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
Ion irradiation study of lithium silicates for fusion blanket applications. 576:154281-154281. 2023
Modeling injected interstitial effects on void swelling in self-ion irradiation experiments (vol 471, pg 200, 2016). 576:154253-154253. 2023
Irradiation response of innovatively engineered metastable TRIP high entropy alloy. 574:154217-154217. 2023
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
An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels. 574:154203-154203. 2022
Orientation-selected micro-pillar compression of additively manufactured 316L stainless steels: Comparison of as-manufactured, annealed, and proton-irradiated variants. 566:153739-153739. 2022
Experimentally validated multiphysics modeling of fracture induced by thermal shocks in sintered UO2 pellets. 565:153719-153719. 2022
Behavior of helium cavities in ion-irradiated W-Ni-Fe ductile-phase toughened tungsten. 561:153565-153565. 2022
Corrosion of 316H stainless steel in flowing FLiNaK salt. 561:153551-153551. 2022
Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium. 561:153519-153519. 2022
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
Healing of nanocracks by collision cascades in nickel. 555:153124-153124. 2021
Validating modern methods for impurity analysis in fluoride salts. 553:152972-152972. 2021
TEM characterization of dislocation loops in proton irradiated single crystal ThO₂. 552:152998-152998. 2021
First steps toward predicting corrosion behavior of structural materials in molten salts. 546:152755-152755. 2021
Heavy ion irradiation response of an additively manufactured 316LN stainless steel. 546:152745-152745. 2021
Atom probe tomography characterization of high-dose ion irradiated MA957. 545:152528-152528. 2021
Helium retention, bubble superlattice formation and surface blistering in helium-irradiated tungsten. 545:152722-152722. 2021
Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding. 544:152695-152695. 2021
Oxide dispersoid coherency of a ferritic-martensitic 12Cr oxide-dispersion-strengthened alloy under self-ion irradiation. 544:152671-152671. 2021
Ni coating on 316L stainless steel using cage plasma treatment: Feasibility and swelling studies. 540:152385-152385. 2020
Hydrothermal corrosion behavior of CVD SiC in high temperature water. 539:152241-152241. 2020
Vacancy and interstitial interactions with crystal/amorphous, metal/covalent interfaces. 539:152329-152329. 2020
Evaluation of the effects of neutron irradiation on first -generation corrosion mitigation coatings on SiC for accident -tolerant fuel cladding *. 536:152203-152203. 2020
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding *. 536:152221-152221. 2020
Radiation response of FeCrAl-coated Zircaloy-4. 536:152175-152175. 2020
The effects of neutron and ionizing corrosion of SiC irradiation on the aqueous. 536:152190-152190. 2020
A threshold density of helium bubbles induces a ductile -to -brittle transition at a grain boundary in nickel. 533:152118-152118. 2020
Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy. 531:151982-151982. 2020
Effect of laser welding on deformation mechanisms in irradiated austenitic stainless steel. 528:151878-151878. 2020
Swelling resistance of advanced austenitic alloy A709 and its comparison with 316 stainless steel at high damage levels. 527:151818-151818. 2019
Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor. 524:119-134. 2019
Tribochemistry of inconel 617 during sliding contact at 950 degrees C under helium environment for nuclear reactors. 521:21-30. 2019
Interface reactions and mechanical properties of FeCrAl-coated Zircaloy-4. 519:57-63. 2019
Compositional effects on radiation tolerance of amorphous silicon oxycarbide. 518:241-246. 2019
Strength and plasticity of amorphous silicon oxycarbide. 516:289-296. 2019
Aggregation and data analysis of corrosion studies in molten chloride and fluoride salts. 511:523-535. 2018
Chemical imaging and diffusion of hydrogen and lithium in lithium aluminate. 511:1-10. 2018
Dispersoid stability in ion irradiated oxide-dispersion-strengthened alloy. 509:504-512. 2018
Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction. 497:10-15. 2017
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
Nanostructural evolution and behavior of H and Li in ion-implanted -LiAlO₂. 494:411-421. 2017
Accelerated corrosion and oxide dissolution in 316L stainless steel irradiated in situ in high temperature water. 493:207-218. 2017
Radiolysis driven changes to oxide stability during irradiation-corrosion of 316L stainless steel in high temperature water. 493:40-52. 2017
Influence of laser shock peening on irradiation defects in austenitic stainless steels. 489:203-210. 2017
Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions. 487:96-104. 2017
Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations. 486:86-95. 2017
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
Radiation response of alloy T91 at damage levels up to 1000 peak dpa. 482:257-265. 2016
Monte Carlo modeling of cavity imaging in pure iron using back scatter electron scanning microscopy. 480:420-428. 2016
Formation, migration, and clustering energies of interstitial He in alpha-quartz and beta-cristobalite. 479:224-231. 2016
High temperature radiation responses of amorphous SiOC/crystalline Fe nanocomposite. 479:411-417. 2016
Modeling injected interstitial effects on void swelling in self-ion irradiation experiments. 471:200-207. 2016
Intermetallic formation and interdiffusion in diffusion couples made of uranium and single crystal iron. 467:82-88. 2015
Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation. 467:42-49. 2015
Measurements of the liquidus surface and solidus transitions of the NaCl-UCl3 and NaCl-UCl3-CeCl3 phase diagrams. 466:280-285. 2015
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450C. 465:343-348. 2015
Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel. 462:191-204. 2015
Superior radiation tolerant materials: Amorphous silicon oxycarbide. 461:200-205. 2015
Radiation effects on interface reactions of U/Fe, U/(Fe plus Cr), and U/(Fe plus Cr plus Ni). 456:302-310. 2015
The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 C. 465:343-348. 2015
Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions. 453:176-181. 2014
He implantation of bulk CuNb nanocomposites fabricated by accumulated roll bonding. 452:57-60. 2014
A facility for studying irradiation accelerated corrosion in high temperature water. 451:40-47. 2014
Measurement of thermal diffusivity of depleted uranium metal microspheres. 446:100-105. 2014
Phase field simulation of grain growth in porous uranium dioxide. 446:90-99. 2014
Phase transformations and defect clusters in single crystal SrTiO3 irradiated at different temperatures. 442:143-147. 2013
Size-dependent radiation tolerance in ion irradiated TiN/AlN nanolayer films. 441:47-53. 2013
Candidate molten salt investigation for an accelerator driven subcritical core. 440:298-303. 2013
Comparisons of radiation damage in He ion and proton irradiated immiscible Ag/Ni nanolayers. 440:310-318. 2013
Coexistence of the and phases in an as-cast uranium-rich UZr alloy. 436:100-104. 2013
Enhanced ion irradiation tolerance properties in TiN/MgO nanolayer films. 434:217-222. 2013
Understanding the phase equilibrium and irradiation effects in Fe-Zr diffusion couples. 432:205-211. 2013
Radiation damage at the coherent anatase TiO2/SrTiO3 interface under Ne ion irradiation. 429:177-184. 2012
Radiation damage in helium ion irradiated nanocrystalline Fe. 425:140-146. 2012
Enhanced radiation tolerance of ultrafine grained Fe-Cr-Ni alloy. 420:235-240. 2012
Helium bubble growth at BCC twist grain boundaries. 419:201-207. 2011
Properties of Helium bubbles in Fe and FeCr alloys. 418:261-268. 2011
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
The U-Ti system: Strengths and weaknesses of the CALPHAD method. 419:177-185. 2011
Thermodynamic study of the Np-Zr system. 409:1-8. 2011
Interface enabled defects reduction in helium ion irradiated Cu/V nanolayers. 407:178-188. 2010
He ion irradiation damage in Fe/W nanolayer films. 389:233-238. 2009
Size dependent enhancement of helium ion irradiation tolerance in sputtered Cu/V nanolaminates. 385:629-632. 2009
Properties of plutonium and its alloys for use as fast reactor fuels. 383:112-118. 2008
Structure of KurdjumovSachs interfaces in simulations of a copperniobium bilayer. 372:45-52. 2008
Amorphization of MgAl2O4 spinel using 1.5 MeV Xe+ ions under cryogenic irradiation conditions. 304:237-241. 2002
Radiation damage effects in zirconia. 274:66-77. 1999
Effects of ionizing radiation in ceramics. 253:113-119. 1998
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
Ion beam analysis of MgAl2O4 spinel irradiated with fast neutrons to 50250 dpa. 239:284-290. 1996
Structure and mechanical properties of irradiated magnesium aluminate spinel. 232:59-64. 1996
Cation disorder in high dose, neutron-irradiated spinel. 219:128-134. 1995
DIFFUSION OF LI-6 ISOTOPES IN LITHIUM ALUMINATE CERAMICS USING NEUTRON DEPTH PROFILING. 203:43-49. 1993
RADIATIVE HEAT-TRANSFER IN POROUS URANIUM-DIOXIDE. 202:87-97. 1993
THE RESULTS OF POSTIRRADIATION EXAMINATIONS OF VVER-1000 AND VVER-440 FUEL-RODS. 178:306-311. 1991
THERMOPHYSICAL PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY. 173:261-273. 1990
TRANSPORT PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY. 173:274-283. 1990
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .2. MECHANICAL-PROPERTIES. 171:271-288. 1990
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .3. TRANSPORT-PROPERTIES. 171:289-299. 1990
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .4. THERMODYNAMIC PROPERTIES. 171:300-318. 1990
PRELIMINARY INVESTIGATIONS OF THE SURFACE-CHEMISTRY OF TITANIUM GETTERING. 123:1151-1155. 1984
Structures and properties of rapidly solidified 9Cr-lMo steel. 122:789-793.
Grain refinement of T91 alloy by equal channel angular pressing 2009
Effect of severe ausforming via equal channel angular extrusion on the shape memory response of a NiTi alloy 2007

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