publication venue for
- Synthesis and characterization of uranium trichloride in alkali-metal chloride media. 565. 2022
- Nd, SbNd and Sb3Nd4 and Their Interactions with the Cladding Alloy HT9. 541:152387. 2020
- Interactions and Immobilization of Lanthanides with Dopants in Uranium-based Metallic Fuels. 540:152372. 2020
- Thermal analysis of projected molten salt compositions during FFTF and EBR-II used nuclear fuel processing. 520:87-95. 2019
- TEM in situ cube-corner indentation analysis using ViBe motion detection algorithm. 502:201-212. 2018
- Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn plus Sb as a mixed additive system to bind lanthanides. 510:210-218. 2018
- Microstructure, mechanical properties and strengthening mechanisms of friction stir welded Kanthal APMT (TM) steel. 509:435-444. 2018
- 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
- TEM in situ micropillar compression tests of ion irradiated oxide dispersion strengthened alloy. 483:107-120. 2017
- A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions. 486:11-20. 2017
- Effects of temperature, concentration, and uranium chloride mixture on zirconium electrochemical studies in LiCI-KCI eutectic salt. 476:176-187. 2016
- Lanthana-bearing nanostructured ferritic steels via spark plasma sintering. 470:297-306. 2016
- Plastic zone size for nanoindentation of irradiated Fe–9%Cr ODS. 481:33-45. 2016
- The effects of oxide evolution on mechanical properties in proton- and neutron-irradiated Fe-9%Cr ODS steel. 479:426-435. 2016
- Microstructural stability of a self-ion irradiated lanthana-bearing nanostructured ferritic steel. 462:191-204. 2015
- Electrochemistry and the mechanisms of nucleation and growth of neodymium during electroreduction from LiCl-KCl eutectic salts on Mo substrate. 458:37-44. 2015
- The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C. 467:97-112. 2015
- Electrochemical studies and analysis of 1-10 wt% UCl3 concentrations in molten LiCl-KCl eutectic. 452:389-396. 2014
- High temperature tensile deformation behavior of Grade 92 steel. 453:151-157. 2014
- Morphological analysis of zirconium nuclear fuel retaining rods braided with SiC: Quality assurance and defect identification. 451:216-224. 2014
- Oxidation and hydrogen uptake in zirconium, Zircaloy-2 and Zircaloy-4: Computational thermodynamics and ab initio calculations. 444:65-75. 2014
- Ultra-high temperature steam corrosion of complex silicates for nuclear applications: A computational study. 444:56-64. 2014
- A preliminary study on the development of La2O3-bearing nanostructured ferritic steels via high energy ball milling. 434:282-286. 2013
- Ferritic oxide dispersion strengthened alloys by spark plasma sintering. 443:256-265. 2013
- Microstructural evolution and mechanical properties of friction stir welded ODS alloy MA754. 442:1-6. 2013
- Microstructure and mechanical properties of friction stir welded oxide dispersion strengthened alloy. 432:274-280. 2013
- Creep deformation mechanisms in modified 9Cr-1Mo steel. 423:110-119. 2012
- Analytical Determination of Thermal Conductivity of W-UO2 and W-UN Cermet Nuclear Fuels. 427:87-94. 2012
- Uncertainty studies of real anode surface area in computational analysis for molten salt electrorefining. 416:318-326. 2011
- Creep behavior of niobium-modified zirconium alloys. 374:354-363. 2008
- Static strain aging and dislocation-impurity interactions in irradiated mild steel. 382:217-222. 2008
- Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. 383:189-195. 2008
- Thermal expansion coefficient of steels used in LWR vessels. 376:211-215. 2008