Zobrazeno 1 - 10
of 44
pro vyhledávání: '"Stephen S Raiman"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 920-926 (2021)
Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on it
Externí odkaz:
https://doaj.org/article/8ffa9a3d4b1e47cf939eac0f1b892f47
Autor:
Juho Lehmusto, J. Matthew Kurley, Ercan Cakmak, James R. Keiser, Daniel Lindberg, Markus Engblom, Bruce A. Pint, Stephen S. Raiman
Publikováno v:
Nuclear Science and Engineering. :1-8
Publikováno v:
Reaction Kinetics, Mechanisms and Catalysis. 129:551-581
While analyses based on the Arrhenius kinetic model have been successfully applied since its introduction, the Arrhenius model neglects to describe pre-exponential factor in a scientifically meaningful fashion. Since the 1930s, transition-state theor
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
Autor:
Jake W. McMurray, J. Matthew Kurley, Adam W. Willoughby, Jiheon Jun, Samuel R. Pearson, Richard T. Mayes, Stephen S. Raiman, Michael J. Lance, Donovan N. Leonard, Harry M. Meyer, Bruce A. Pint
Publikováno v:
Materials and Corrosion. 70:1439-1449
Publikováno v:
SSRN Electronic Journal.
Ni-Cr alloys exhibit oscillatory segregation behaviors at low index surfaces, in which the preferred segregation species changes from Ni in the first layer to Cr in the second layer. In many dilute alloy systems, this oscillatory pattern is attribute
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 920-926 (2021)
Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on it
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d67df7064351eea95644f3e2fbf3488e
https://engrxiv.org/e3yru
https://engrxiv.org/e3yru
Autor:
Muhammad Anas, Huaixuan Cao, Ju Hyun Oh, Anubhav Sarmah, Carolyn T. Long, Mohammad U. F. Khan, Stephen S. Raiman, Miladin Radovic, Micah J. Green
Publikováno v:
Advanced Engineering Materials. 24:2101383
Autor:
Stephen S. Raiman, Sangkeun Lee
Publikováno v:
Journal of Nuclear Materials. 511:523-535
Corrosion studies in molten fluoride and chloride salts were surveyed, and key data were aggregated into a single dataset. Studies were graphed by salt purity, temperature, sample material, container material, and experimental method (loop, capsule,
Publikováno v:
CORROSION. 75:217-223
SiC/SiC ceramic matrix composites are an attractive material for use as accident tolerant fuel cladding. However, despite its resistance to corrosion in high-temperature steam, SiC is known to diss...