Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Jo Jo Lee"'
Publikováno v:
Corrosion Science. :111301
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8e84fc90a506e16650b9a7d242152a5c
https://doi.org/10.1016/j.corsci.2023.111301
https://doi.org/10.1016/j.corsci.2023.111301
Autor:
Takaaki Koyanagi, Stephen S. Raiman, Cristian I. Contescu, Jo Jo Lee, Xunxiang Hu, Ying Yang, Yutai Katoh
Publikováno v:
Journal of Nuclear Materials. 524:119-134
Silicon carbide is widely appreciated for its high temperature strength, radiation tolerance and neutronic transparency in applications for fuel particles and core internals of nuclear reactors. In the Fluoride Salt-Cooled High Temperature Reactor, s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c368bc254bd7fa3a31b85be10ab3f9c
https://doi.org/10.1016/j.jnucmat.2019.07.001
https://doi.org/10.1016/j.jnucmat.2019.07.001
Publikováno v:
Journal of Nuclear Materials. 500:64-71
The oxidation rates of several nuclear-grade graphites, NBG-18, NBG-17, IG-110 and IG-11, were measured in air using thermogravimetry. Kinetic parameters and oxidation behavior for each grade were compared by coke type, filler grain size and microstr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b55f4dcd97c703ad370d3cdcee846ac0
https://doi.org/10.1016/j.jnucmat.2017.11.053
https://doi.org/10.1016/j.jnucmat.2017.11.053
Autor:
Yoonjo Jo Jo Lee1, Simones, Matthew Paul2, Kennedy, John C.1, Us, Hakan, Makarewicz, Philip F.1, Neher, Janese Annetta3, Prelas, Mark A.4
Publikováno v:
Proceedings of the ASEE Annual Conference & Exposition. 2014, p1-29. 29p.
Autor:
Jo Jo Lee, Cristian I. Contescu, José David Arregui-Mena, Yutai Katoh, Timothy D. Burchell, Sudarshan K. Loyalka
Publikováno v:
Journal of Nuclear Materials. 534:152119
The reactor core, moderator and reflectors of a thermal spectrum advanced molten salt reactor will constitute multi-tons of graphite. Porous reactor-grade graphite, if unprotected, can be permeated by molten salt depending on the infiltrating pressur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33c8acafde1e66515818a8997e900d39
https://doi.org/10.1016/j.jnucmat.2020.152119
https://doi.org/10.1016/j.jnucmat.2020.152119
Publikováno v:
Journal of Nuclear Materials. 451:48-54
Data on oxidation rates of matrix-grade graphite in the kinetically-controlled temperature regime of graphite oxidation are needed for safety analysis of High Temperature Gas Cooled Reactors and Very High Temperature Reactors. In this work, the oxida
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ecba3a4bb9b2bd7bfaa0b825ef709c0
https://doi.org/10.1016/j.jnucmat.2014.03.033
https://doi.org/10.1016/j.jnucmat.2014.03.033
Publikováno v:
Journal of Nuclear Materials. 446:38-48
The oxidation rates of nuclear-grade graphite IG-110 in the kinetically-controlled temperature regime of graphite oxidation were predicted and compared in Very High Temperature Reactor air ingress accident scenarios. The oxidative mass loss of graphi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::38d03bb47933d95e967fdff998870724
https://doi.org/10.1016/j.jnucmat.2013.11.032
https://doi.org/10.1016/j.jnucmat.2013.11.032
Publikováno v:
Journal of Nuclear Materials. 438:77-87
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34f584f22ab46fe579c55e2f5b42fcb1
https://doi.org/10.1016/j.jnucmat.2013.03.002
https://doi.org/10.1016/j.jnucmat.2013.03.002