Zobrazeno 1 - 10
of 26
pro vyhledávání: '"N.A.P. Kiran Kumar"'
Publikováno v:
Journal of Nuclear Materials. 518:208-225
To collect data for fusion applications and understand the basic properties of tungsten, single-crystal tungsten was neutron irradiated in the mixed-spectrum High Flux Isotope Reactor at the Oak Ridge National Laboratory at temperatures of 90–830
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::563758e8868cff6c4c5b30778af0bc62
https://doi.org/10.1016/j.jnucmat.2019.02.050
https://doi.org/10.1016/j.jnucmat.2019.02.050
Autor:
Xunxiang Hu, Lance Lewis Snead, Yutai Katoh, Takaaki Koyanagi, Taehyun Hwang, Lauren M. Garrison, N.A.P. Kiran Kumar
Publikováno v:
Journal of Nuclear Materials. 490:66-74
Microstructures of single-crystal bulk tungsten (W) and polycrystalline W foil with a strong grain texture were investigated using transmission electron microscopy following neutron irradiation at ∼90–800 °C to 0.03–4.6 displacements per atom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2bdc85f440a13a8a153adca2b711b1ce
https://doi.org/10.1016/j.jnucmat.2017.04.010
https://doi.org/10.1016/j.jnucmat.2017.04.010
Autor:
Yutai Katoh, Lauren M. Garrison, Takaaki Koyanagi, Makoto Fukuda, Akira Hasegawa, Lance Lewis Snead, N.A.P. Kiran Kumar
Publikováno v:
Journal of Nuclear Materials. 479:249-254
Neutron irradiation to single crystal pure tungsten was performed in the mixed spectrum High Flux Isotope Reactor (HFIR). To investigate the influences of neutron energy spectrum, the microstructure and irradiation hardening were compared with previo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::efe923a4aa7230d65f9d90e8a3b23351
https://doi.org/10.1016/j.jnucmat.2016.06.051
https://doi.org/10.1016/j.jnucmat.2016.06.051
Publikováno v:
Acta Materialia. 113:230-244
In recent years, high entropy alloys (HEAs) have attracted significant attention due to their excellent mechanical properties and good corrosion resistance, making them potential candidates for high temperature fission and fusion structural applicati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e86da04c5f5a4d0ce9076a53a32d4430
https://doi.org/10.1016/j.actamat.2016.05.007
https://doi.org/10.1016/j.actamat.2016.05.007
Publikováno v:
Materials Science and Engineering: A. 637:48-55
In-situ electron backscatter diffraction of low stacking fault energy 316L austenitic stainless steel was carried out in tension to study the evolution of microstructure and micro-texture as a function of strain till fracture. The microstructure was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7a173dc5e4997a747a56aea229c259f2
https://doi.org/10.1016/j.msea.2015.04.005
https://doi.org/10.1016/j.msea.2015.04.005
Publikováno v:
Fusion Science and Technology. 67:771-783
The study presents the high-dose behavior of dielectric mirrors specifically engineered for radiation-tolerance: alternating layers of Al2O3/SiO2 and HfO2/SiO2 were grown on sapphire substrates and exposed to neutron doses of 1 and 4 dpa at 458 10K i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::649a3e4cd827cf5ea106e7bdd1c5ca27
https://doi.org/10.13182/fst14-875
https://doi.org/10.13182/fst14-875
Publikováno v:
Acta Materialia. 81:219-229
Hydride-induced ductile-to-brittle transition is an important feature for the failure of hydride-forming materials. Although this problem has been studied for many years, its relation to microstructure remains unclear. The degree of hydride-induced e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e9faad30648a1e40d5fdb5438f4e862
https://doi.org/10.1016/j.actamat.2014.08.010
https://doi.org/10.1016/j.actamat.2014.08.010
Publikováno v:
Journal of Nuclear Materials. 445:281-290
Dielectric mirrors of HfO 2 /SiO 2 and Al 2 O 3 /SiO 2 designed for optimum reflectivity at 248 nm with 11 and 30 bi-layer coatings, respectively, survived irradiation to 0.1 dpa at 448 K without film cracking or delamination from their sapphire subs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f3be9182e3270f893e5c14424fa4eef0
https://doi.org/10.1016/j.jnucmat.2013.11.022
https://doi.org/10.1016/j.jnucmat.2013.11.022
Publikováno v:
Journal of Nuclear Materials. 427:343-349
This review article attempts to provide an overall description for the texture related issues of degradation of Zr alloys. Experimental observations show that the oxide formed on Zr alloys is strongly textured. The texture and grain-boundary characte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::af9c7f33d6d1f0bba14ebd689afc2cf3
https://doi.org/10.1016/j.jnucmat.2012.05.005
https://doi.org/10.1016/j.jnucmat.2012.05.005
Publikováno v:
Acta Materialia. 59:7010-7021
A theoretical understanding of the intergranular δ-hydrides is still lacking, although hydride-related degradation of the mechanical properties of zirconium alloys has been studied for many years. In this paper a thermodynamic model is developed to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d2a4f68a3231152fd27e0b54059f1c6b
https://doi.org/10.1016/j.actamat.2011.07.054
https://doi.org/10.1016/j.actamat.2011.07.054