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Otsuka, Hideo; Hojo, Kiichi; Maeta, Hiroshi*; Otsu, Hitoshi; Sugai, Hiroyuki; Yamamoto, Hiroyuki
European Physical Journal D, 16(1-3), p.309 - 311, 2001/09
no abstracts in English
Mizuta, Shunji; ;
JNC TN9400 2000-048, 28 Pages, 2000/04
JNC-TN9400-2000-048.pdf:0.64MB
ODS (Oxide Dispersion Strengthened) ferritic-martainsitic steels are one of the most prospective cladding materials for advanced fast breeder reactors, since they are expected to have excellent swelling resistance and superior high temperature strength due to the finely distributed stable oxide particles(Y
O
). Properties and the tentative strength equations for ODS ferritic-martainsitic were proposed on the basis of the latest data to apply to the feasibility study of the sodium coolant MOX fuel plant. The items of equations are follows. (1)creep rupture strength (2)correction factor of creep rupture strength (in Na and in reactor) (3)outer surface eorrosion (Na) (4)inner surface corrosion (in MOX fuel pin) (5)thermal conductivity
Yamashita, Shinichiro; Ioka, Ikuo; Oka, Hiroshi*; Isobe, Shigehito*; Hashimoto, Naoyuki*
no journal, ,
The objective of this work is the development of new reduced activation HEAs applicable to next generation small module reactor components by using additive manufacturing (3D printing) method under the support of the 2020 MEXT Innovative Nuclear Research and Development Program. In the third presentation, we will share the highlighted results on radiation properties of the newly developed HEAs in this work.
Hashimoto, Naoyuki*; Ueda, Mikito*; Hayashi, Shigenari*; Oka, Hiroshi*; Isobe, Shigehito*; Yamashita, Shinichiro; Itakura, Mitsuhiro; Tsuru, Tomohito
no journal, ,
The objective of this work is the development of new reduced activation HEAs applicable to next generation small module reactor components by using additive manufacturing (3D printing) method under the support of the 2020 MEXT Innovative Nuclear Research and Development Program. We firstly introduce the outline of this work as a part of the series presentation.
Oka, Hiroshi*; Sato, Motoki*; Hashimoto, Naoyuki*; Isobe, Shigehito*; Yamashita, Shinichiro
no journal, ,
The objective of this work is the development of new reduced activation HEAs applicable to next generation small module reactor components by using additive manufacturing (3D printing) method under the support of the 2020 MEXT Innovative Nuclear Research and Development Program. In the second presentation, we will share the highlighted results on mechanical properties as well as microstructure of the newly developed HEAs in this work.
Yamashita, Shinichiro; Ioka, Ikuo; Abe, Yosuke; Oka, Hiroshi*; Isobe, Shigehito*; Hashimoto, Naoyuki*
no journal, ,
The objective of this work is the development of new reduced activation HEAs applicable to next generation small module reactor components by using additive manufacturing (3D printing) method under the support of the 2020 MEXT Innovative Nuclear Research and Development Program. In the third presentation, we will share the highlighted results on radiation properties of the newly developed HEAs in this work.
-phase based titanium alloysWakai, Eiichi; Ishida, Taku*; Kano, Sho*; Shibayama, Tamaki*; Sato, Koichi*; Noto, Hiroyuki*; Makimura, Shunsuke*; Furuya, Kazuyuki*; Yabuuchi, Atsushi*; Yoshiie, Toshimasa*; et al.
no journal, ,
Titanium materials have been applied to beam window materials and beam dumps in large accelerator systems because of their low specific gravity, high corrosion resistance, strength, and other advantages. As the beam power becomes higher, further improvement of irradiation resistance is required. We have investigated further the properties of titanium alloys based on the -phase, and it was found that Ti-15-3-3-3 alloys have excellent irradiation resistance when subjected to ion irradiation. In order to investigate the cause of this, microstructures and point defects in this and related materials were evaluated by TEM, positron lifetime measurement, electrical resistivity, and stress-induced changes, among others. In addition, we have recently begun to develop a prototype of a titanium-based high-entropy alloy based on -titanium, which is attracting worldwide attention and is being developed, and have also begun to evaluate the emotional properties of this alloy. We have examined the various properties of this material and found that it has considerably higher strength than conventional iron- and titanium-based materials.