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Yano, Yasuhide; Tanno, Takashi; Oka, Hiroshi; Otsuka, Satoshi; Kaito, Takeji
Journal of Nuclear Materials, 555, p.153105_1 - 153105_8, 2021/11
Times Cited Count：1 Percentile：15.7(Materials Science, Multidisciplinary)The aim of this study was to evaluate the tensile properties and microstructures of dissimilar welds between 11Cr-ferritic/martensitic steel and 316 stainless steel after thermal aging at temperatures between 400 and 600
C up to 30,000 h. Characterization of microstructure was carried out by scanning electron microscopy and transmission electron microscopy. Microstructural analysis showed that the microstructure in the weld metals consisted of lath martensite containing a small amount of residual austenite. Thermal aging hardening of WMs occurred at 400 and 450C due to the effects of both a-a' phase separation and G-phase precipitation. However, there was no significant change in the total elongation, and fracture surfaces indicated that very fine dimpled rupture was predominant rather than the cleavage rupture. It was suggested that lath martensite phases enhanced the tensile strength due to phase separation, while residual austenite played a role in keeping elongation as a soft phase.
Kawamura, Hiroshi
JAERI-Review 2002-011, 165 Pages, 2002/06
JAERI-Review-2002-011.pdf:28.71MB
no abstracts in English
Furuya, Kazuyuki; Enoeda, Mikio
Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.442 - 447, 1998/05
no abstracts in English
; Shiba, Kiyoyuki; Hishinuma, Akimichi
JAERI-Tech 97-061, 46 Pages, 1997/11
no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi;
Fusion Technology, 2, p.1399 - 1402, 1996/00
no abstracts in English
Yuzawa, Sho*; Yabuuchi, Kiyohiro*; Kimura, Akihiko*; Sakamoto, Kan*; Hirai, Mutsumi*; Yamashita, Shinichiro
no journal, ,
Oxide dispersion strengthened steel with high Cr and Al concentration in chemical composition (FeCrAl-ODS steel) has been proposed as a promising candidate for the accident tolerant fuel cladding of light water reactors (LWRs) because of their excellent oxidation and corrosion resistance under high temperature water and steam environments. Neither there are no sufficient knowledge on welding technology of FeCrAl-ODS nor it is known that aluminum addition remarkably degrades the weldability of the ODS steel. In this study, electron beam (EB) welding and tungsten inert gas (TIG) welding were applied to the SUS430 endcap welding to cladding tube made of FeCrAl-ODS steel and performed the bonding strength and corresponding damage structure evaluations at the bonding part.
Ishibashi, Ryo*; Ikegawa, Tomohiko*; Tanabe, Shigetada*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
For the purpose of improving corrosion resistance of silicon carbide (SiC) in boiling water reactor (BWR) environments, corrosion resistant coatings to SiC substrate were evaluated. Due to its lower hydrogen generation rate and lower reaction heat in comparison with a conventional zircaloy, SiC is expected to be a proper material for accident tolerant fuel. On the other hand, there are still a lot of critical issues left for the practical application of SiC fuel cladding and fuel channel box, one of which is hydrothermal corrosion. In this study, corrosion behavior of candidate coatings to SiC substrate and joint portion were evaluated in unirradiated high purity water environments.
