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Ukai, Shigeharu; Kaito, Takeji; Otsuka, Satoshi; Fujiwara, Masayuki*; Kobayashi, Toshimi*
Materia, 45(1), p.48 - 50, 2006/01
Development of 9Cr-ODS ferritic/martensitic steel cladding was introduced as a new technology applied onece a year by Japan Institute of Metal. This cladding was developed by JAEA, and manufacturing of cladding was originally attained by controlling microstructure. Its high temperature strength is the most superior in the world as a heat resistance ferritic steels.
Narita, Takeshi; Ukai, Shigeharu; Kaito, Takeji; Otsuka, Satoshi; Kobayashi, Toshimi*
Proceedings of 11th International Conference on Fusion Reactor Materials (ICFRM-11), 41(10), 0 Pages, 2004/00
Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.
; Mizuta, Shunji; Yoshitake, Tsunemitsu; *
The Sixth Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engine, 0 Pages, 2001/00
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; Mizuta, Shunji; Yoshitake, Tsunemitsu; *
9th International Conference on Fusion Reactor Materials, 0 Pages, 1999/00
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Ito, Takushi; Kato, Shoichi; Aoki, Masanori; Yoshida, Hidekazu; Kobayashi, Toshimi; Wada, Yusaku
Journal of Nuclear Science and Technology, 29(4), p.367 - 377, 1992/04
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Shimoyama, Kazuhito; ; Usami, Masayuki; Tanabe, Hiromi; Yoshida, Eiichi; *
PNC TN9410 91-288, 72 Pages, 1991/07
For the development of a once-through unit type steam generator for an FBR, materials having a high mechanical strength at elevated temperatures and high resistivity against stress corrosion cracking (scc) are needed as its heat transfer tubes. High-chrome ferritic steels such as Mod.9Cr-1Mo, 9cr-2Mo, and 9Cr-1Mo-Nb-V steel are considered to meet these requirements. As previously reported, there was not large difference of resistivity among these materials and it was confirmed that high-chrome ferritic steels were more wastage -resistant than the 2.25Cr-1Mo steel which is a representative ferritic steel as tube materials. Since wastage data of weld portion at which the initial leak is apt to occur had been insufficient in order to totally evaluate the wastage resistivity of the high-chrome ferritic steels wastage tests in the micro-leak and small leak ranges were conducted for the tube-tube weld point of Mod.9Cr-1Mo steel. Major results are as follows : (1)In the micro-leak tests, there are not large differences in the self-wastage resistivity between the weld and the base metal. And the wastage resistivity is independant of the location of the leak starting point (a weld metal, a bond of weld, or a heat affected zone). (2)In the small leak tests, there are not large differences in the wastage resistivity between the weld and the base material. In the results, the empirical formula of wastage rate that derived from the base materials of the high-chrome ferritic steel can also be applied to the heat transfer tubes including the weld materials.
Wada, Yusaku; Yoshida, Eiichi; Kobayashi, Toshimi; Aoto, Kazumi
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles, ,
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