Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Peter A. Mouche"'
Autor:
Peter A. Mouche, Padraig Stack, K. Montoya, Kenneth Kane, Danny Schappel, Elizabeth Sooby, Kurt A. Terrani
Publikováno v:
Journal of the American Ceramic Society. 104:2225-2237
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::61b6100d29e9b9acf6f1a99703f7335a
https://doi.org/10.1111/jace.17632
https://doi.org/10.1111/jace.17632
Autor:
Peter A. Mouche, Kurt A. Terrani
Publikováno v:
Journal of the American Ceramic Society. 103:2062-2075
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::61209b6f7b390cb3c5c4989d73e20fb2
https://doi.org/10.1111/jace.16834
https://doi.org/10.1111/jace.16834
Autor:
Simerjeet K. Gill, Mohamed Elbakhshwan, Weicheng Zhong, Xiang Liu, Dong Hee Park, James F. Stubbins, Jun Li Lin, Peter A. Mouche, Brent J. Heuser, Yang Ren
Publikováno v:
Metallurgical and Materials Transactions A. 50:1851-1861
The stability of intermetallic second-phase particles (SPPs) in coated Zircaloy-2 was studied in 700 °C steam environments up to 20 hours. Hydrogen generated from high-temperature steam oxidation of uncoated Zr-induced δ-hydrides formation in the Z
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ec0c4d29ddea26a697a93c8e48c7fb36
https://doi.org/10.1007/s11661-018-5090-5
https://doi.org/10.1007/s11661-018-5090-5
Publikováno v:
Transactions of the American Nuclear Society - Volume 123.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae44b87f69756aa01c9a2ec7ee480f91
https://doi.org/10.13182/t123-32923
https://doi.org/10.13182/t123-32923
Autor:
Brent J. Heuser, Peter A. Mouche
Publikováno v:
Oxidation of Metals. 91:259-277
The steam oxidation kinetics, oxide formation, and hydrogen uptake of nuclear-grade Zr with 0.01–12 wt% yttrium were studied. Metallography and diffraction of the as-received material showed yttrium remained trapped in solid solution in concentrati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9039777da89d7304b430cb0aaa1e1b90
https://doi.org/10.1007/s11085-018-9878-x
https://doi.org/10.1007/s11085-018-9878-x
Autor:
Brent J. Heuser, Weicheng Zhong, Hoon Taek Lee, Peter A. Mouche, Kuan Che Lan, James F. Stubbins, Hsiao-Ming Tung
Publikováno v:
Journal of Microscopy. 272:25-34
This work presents a methodology combining SEM, EDS, conventional EBSD, and transmission-EBSD to analyse a recrystallised Zircaloy-4 sheet and cold-worked stress-relieved (CWSR) Zircaloy-4 cladding in unprecedented detail. Second-phase precipitates (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8cadbf9a73ec7f30cfd5e47771c05669
https://doi.org/10.1111/jmi.12729
https://doi.org/10.1111/jmi.12729
Autor:
Gary S. Was, Dong Hee Park, Kiran K. Mandapaka, Peter A. Mouche, Weicheng Zhong, Brent J. Heuser
Publikováno v:
Journal of Nuclear Materials. 502:95-105
FeAl(Cr) thin-film depositions on Zircaloy-2 were studied using transmission electron microscopy (TEM) and scanning transmission electron microscopy (STEM) with respect to oxidation behavior under simulated boiling water reactor (BWR) conditions and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2342ffd74f4d555fe23e9c457ce9152
https://doi.org/10.1016/j.jnucmat.2018.01.055
https://doi.org/10.1016/j.jnucmat.2018.01.055
Publikováno v:
Journal of Nuclear Materials. 498:137-148
The oxidation behavior of chromium (Cr) and chromium-aluminum (CrAl) coatings with various compositions deposited on Zircaloy-2 to 700 °C high-temperature steam (HTS) exposure has been investigated. CrAl coatings with higher Al compositions demonstr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a4807e24be670ccf0cffb21fb7570292
https://doi.org/10.1016/j.jnucmat.2017.10.021
https://doi.org/10.1016/j.jnucmat.2017.10.021
Publikováno v:
Journal of Nuclear Materials. 556:153251
Swelling of SiC at 300 ∘ C due to in-service neutron irradiation causes tensile residual stresses in coatings which are expected to adversely affect the performance of coated SiC composite fuel cladding for light water reactors. Matching the coatin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::226b81f3c5b8b97cbda6b860e7577596
https://doi.org/10.1016/j.jnucmat.2021.153251
https://doi.org/10.1016/j.jnucmat.2021.153251