Zobrazeno 1 - 10
of 141
pro vyhledávání: '"J.P Robertson"'
Autor:
Tatsuya Hinoki, Masafumi Akiyoshi, Yutai Katoh, Lauren M. Garrison, Hsin Wang, Eric Lang, Emily Proehl, Takaaki Koyanagi, Xunxiang Hu, Makoto Fukuda, Chad M. Parish, Joel Lee McDuffee, Josina W. Geringer, J.P Robertson, Akira Hasegawa, Michael Mcalister, Takeshi Miyazawa, Xiang Chen, Nathan Reid
Publikováno v:
Fusion Science and Technology. 75:499-509
The United States and Japan have collaborated on fusion materials research in a series of agreements reaching back to 1981. The PHENIX collaboration is the latest U.S.-Japan project which s...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5c342a3ca5b97a4701fbef116712adb7
https://doi.org/10.1080/15361055.2019.1602390
https://doi.org/10.1080/15361055.2019.1602390
Autor:
Yutai Katoh, Mikhail A. Sokolov, J.P Robertson, Xiang Chen, Josina W. Geringer, Logan A. Clowers, Michael Rieth, Anne A. Campbell, Tim Graening, Arunodaya Bhattacharya
Publikováno v:
DOE / OSTI
Volume 1: Codes and Standards
Volume 1: Codes and Standards
In this study, we performed fracture toughness characterization of ten neutron-irradiated Eurofer97 variants using precracked miniature multi-notch bend bar (M4CVN) specimens based on the Master Curve method in the ASTM E1921 standard. The neutron ir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7d2cd4d21757f95d575ffaa5763bab14
https://doi.org/10.1115/pvp2020-21312
https://doi.org/10.1115/pvp2020-21312
Autor:
Meredith J.P. Robertson
Publikováno v:
Paediatrics and Child Health. 26:362-365
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::741c9e7046e972f796e035f3bcc36d8a
https://doi.org/10.1016/j.paed.2016.04.004
https://doi.org/10.1016/j.paed.2016.04.004
Autor:
Hiroyasu Tanigawa, Mikhail A. Sokolov, Xiang Chen Frank, Josina W. Geringer, M. Ando, J.P Robertson, Yutai Katoh
Publikováno v:
Journal of Nuclear Materials. 542:152501
F82H is the Japanese reference reduced-activation ferritic-martensitic (RAFM) steel for fusion blanket applications. The harsh environment of a fusion reactor, such as neutron irradiation and He/H damage, can result in significant degradation of F82H
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d7af886ed2a7057c4d56dad4784c75e0
https://doi.org/10.1016/j.jnucmat.2020.152501
https://doi.org/10.1016/j.jnucmat.2020.152501
Publikováno v:
British Journal of Dermatology. 173:835-837
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::380e34b063cce8c9a22503e8905b6997
https://doi.org/10.1111/bjd.13782
https://doi.org/10.1111/bjd.13782
Akademický článek
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Autor:
Kenji Abiko, Y Miwa, Naoyuki Hashimoto, Koreyuki Shiba, Ronald L. Klueh, Shiro Jitsukawa, Eiichi Wakai, J.P Robertson, S Furuno
Publikováno v:
Journal of Nuclear Materials. :203-211
The synergistic effect of displacement damage and hydrogen or helium atoms on microstructures in F82H steel irradiated at 250–400 °C to 2.8–51 dpa in HFIR has been examined using isotopes of 54 Fe or 10 B . Hydrogen atoms increased slightly the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::012c7ecf142396b45b9f2fb6a289fc74
https://doi.org/10.1016/s0022-3115(02)01261-8
https://doi.org/10.1016/s0022-3115(02)01261-8
Autor:
David S. Gelles, Margaret L. Hamilton, Lawrence R. Greenwood, Akira Kohyama, Koreyuki Shiba, Brian M. Oliver, Somei Ohnuki, J.P Robertson, Yutaka Kohno
Publikováno v:
Journal of Nuclear Materials. :212-216
An alloy of F82H prepared using the isotope 54Fe in order to encourage H and He production in a fission reactor has been irradiated in the HFIR JP20 experiment at three temperatures to 7 dpa as TEM disks. Irradiated disks were shear punch tested, exa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::caa3ec3d14dd94f44e009b98cfbfbdcf
https://doi.org/10.1016/s0022-3115(02)01181-9
https://doi.org/10.1016/s0022-3115(02)01181-9
Publikováno v:
Journal of Nuclear Materials. :352-356
The effects of cold working and impurities on swelling behavior in austenitic stainless steels irradiated at 400 °C to 17.3 dpa under spectrally tailored conditions in the Oak Ridge research reactor and high flux isotope reactor were investigated. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d53c22af65be13477c8a0cc4cbe8a749
https://doi.org/10.1016/s0022-3115(02)01189-3
https://doi.org/10.1016/s0022-3115(02)01189-3