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pro vyhledávání: '"S Jitsukawa"'
Autor:
I Nagai
Publikováno v:
JAPANES JOURNAL OF MEDICAL INSTRUMENTATION. 62:55-56
Akademický článek
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Autor:
Roger E. Stoller, Farong Wan, G.R. Odette, J. Konys, Lizhen Tan, Akihiko Kimura, Yican Wu, Takeo Muroga, Y. Dai, Takuya Yamamoto, Qunying Huang, Nadine Baluc, Baldev Raj, A.-A.F. Tavassoli, Hiroyasu Tanigawa, Richard J. Kurtz, S. Jitsukawa, Rainer Lindau
Publikováno v:
Journal of Nuclear Materials. 442:S2-S8
Several types of reduced activation ferritic/martensitic (RAFM) steel have been developed over the past 30 years in China, Europe, India, Japan, Russia and the USA for application in ITER test blanket modules (TBMs) and future fusion DEMO and power r
Publikováno v:
Scopus-Elsevier
It is known that the presence of even a small amount of impurity in interstitial positions can, depending on temperature, have a drastic influence on the one-dimensional (1-D) motion of sel...
Publikováno v:
Fusion Engineering and Design. 86:2895-2899
Thermal aging properties of reduced activation ferritic/martensitic steel F82H was researched. The aging was performed at temperature ranging from 400 °C to 650 °C up to 100,000 h. Microstructure, precipitates, tensile properties, and Charpy impact
Publikováno v:
Journal of Nuclear Materials. 417:270-273
The radiation-hardening of oxide dispersion strengthened (ODS) alloys was examined using ion irradiation and nano-indentation. In this work, three ODS steels were irradiated in the TIARA facility at JAEA with 10.5 MeV Fe 3+ ions up to a dose of 20 dp
Autor:
H. Kimura, Takeo Muroga, P. Garin, M. Zmitko, E. Diegele, R. Heidinger, Anton Möslang, Yves Poitevin, Masayoshi Sugimoto, S. Jitsukawa, Takeo Nishitani, Angel Ibarra
Publikováno v:
Fusion Engineering and Design. 86:611-614
This paper summarizes the proposals and findings of the IFMIF Specification Working Group established to update the users requirements and top level specifications for the facility. Special attention is given to the different roadmaps of fusion pathw
Autor:
Roger E. Stoller, S. Jitsukawa, Mikhail A. Sokolov, Hiroyasu Tanigawa, Anton Möslang, Richard J. Kurtz, G.R. Odette, Kiyoyuki Shiba, Rainer Lindau
Publikováno v:
Journal of Nuclear Materials. 417:9-15
The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion energy demonstration reactor blankets. This includes manufacturing technology, the as-fabricat
Publikováno v:
Journal of Nuclear Materials. 417:1090-1093
Embrittlement is known to be caused by P segregation at grain boundaries in Fe alloys. Effects of P substitutions on binding energies and electronic structures of octahedral Fe cluster are investigated using density functional calculations in order t
Publikováno v:
Fusion Engineering and Design. 86:2549-2552
Reduced activation ferritic/martensitic (RAFM) steels are recognized as the primary candidate structural materials for fusion blanket systems. Because of the possibility of creating sound engineering bases, such as a suitable fabrication technology a