Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Alicia G. Certain"'
Autor:
Alicia G. Certain, Shyam Dwaraknath, Mychailo B. Toloczko, Frank A. Garner, Roger E. Stoller, Gary S. Was
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 459:196-197
Autor:
Zhijie Jiao, Alicia G. Certain, Gary S. Was, Kevin G. Field, Arthur T. Motta, Janelle P. Wharry, Leland Barnard, Todd R. Allen, Brian D. Wirth, Dane L. Morgan, Cem Topbasi, Yong Yang, Aaron A. Kohnert, Djamel Kaoumi
Publikováno v:
Journal of Materials Research. 30:1246-1274
Designing materials for performance in high-radiation fields can be accelerated through a carefully chosen combination of advanced multiscale modeling paired with appropriate experimental validation. The studies reported in this work, the combined ef
Publikováno v:
Journal of Materials Research. 30:1275-1289
This paper provides an overview of advanced scanning transmission electron microscopy (STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced STEM methods provide the high-resolution imaging and chemical analysis neces
Autor:
Farong Wan, Jianchao He, Kumar Sridharan, Todd R. Allen, Vaithiyalingam Shutthanandan, Alicia G. Certain, Yaqiao Wu
Publikováno v:
Journal of Nuclear Materials. 455:41-45
14YWT oxide dispersion strengthened (ODS) ferritic steel was irradiated with of 5 MeV Ni2+ ions, at 300 °C, 450 °C, and 600 °C to a damage level of 100 dpa. The stability of Ti–Y–O nanoclusters was investigated by applying atom probe tomograph
Publikováno v:
Journal of Nuclear Materials. 452:87-94
The stability of Y–Ti–O nanoclusters, dislocation structure, and grain boundary segregation in 9Cr-ODS steels has been investigated following proton irradiation at 400 °C with damage levels up to 3.7 dpa. A slight coarsening and a decrease in nu
Autor:
Shyam Dwaraknath, Alicia G. Certain, Frank A. Garner, Mychailo B. Toloczko, R. E. Stoller, Gary S. Was
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 310:75-80
The SRIM (formerly TRIM) Monte Carlo simulation code is widely used to compute a number of parameters relevant to ion beam implantation and ion beam processing of materials. It also has the capability to compute a common radiation damage exposure uni
Autor:
Satyanarayana V N T Kuchibhatla, Todd R. Allen, Vaithiyalingam Shutthanandan, David T. Hoelzer, Alicia G. Certain
Publikováno v:
Journal of Nuclear Materials. 434:311-321
Nanostructured oxide dispersion strengthened (ODS) steels are considered candidates for nuclear fission and fusion applications at high temperature and dose. The complex oxide nanoclusters in these alloys provide high-temperature strength and are exp
Publikováno v:
Journal of Nuclear Materials. 432:281-286
Molecular dynamics (MD) simulations have been used to investigate the re-solution of copper atoms from coherent, nanometer-sized copper precipitates in a body-centered cubic iron matrix. The molecular dynamics simulations used Finnis–Sinclair type
Publikováno v:
The Journal of chemical physics. 145(10)
Studies of solute precipitation and precipitate phase stability in nuclear structural materials under concurrent irradiation and heat often lead to contradictory results due to the complex nature of the phenomena which is far from well understood. He
Autor:
Michael K Miller, James Bentley, Jeremy T Busby, Todd R. Allen, Alicia G. Certain, Kevin G. Field
Publikováno v:
Journal of Nuclear Materials. 407:2-9
Ferritic–martensitic (F/M) alloys are expected to play an important role as cladding or structural components in Generation IV and other advanced nuclear systems operating in the temperature range 350–700 °C and to doses up to 200 displacements