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Nakano, Hiroko; Shibata, Hiroshi; Takeuchi, Tomoaki; Matsui, Yoshinori; Tsuchiya, Kunihiko
Proceedings of International Conference on Asia-Pacific Conference on Fracture and Strength 2016 (APCFS 2016) (USB Flash Drive), p.283 - 284, 2016/09
no abstracts in English
Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*
Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09
Times Cited Count：5 Percentile：36.38(Materials Science, Multidisciplinary)In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.
Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*
Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04
Times Cited Count：5 Percentile：35.8(Materials Science, Multidisciplinary)This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.
Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Wakai, Eiichi; Miura, Kuniaki*
Journal of Nuclear Materials, 318(1-3), p.348 - 354, 2003/05
Times Cited Count：28 Percentile：84.98(Materials Science, Multidisciplinary)Corrosion test of austenitic stainless tube was done under the flowing Pb-Bi condition during 3000 hrs at 450
C. Specimen is 316SS produced as a tubing form with 13.8 mm outer diameter, 2 mm thickness and 40 cm length. During the operation, maximum temperature, temperature difference and flow velocity of Pb-Bi at the specimen were kept at 450C, 50C, and 1m/s, respectively. After the test, specimen and components of the loop were cut and examined by optical microscope, SEM, EDX, WDX and X-ray diffraction. Pb-Bi adhered on the surface of the specimen even after Pb-Bi was drained out to the storage tank from the circulating loop. Different results from a stagnant corrosion test were that the specimen surface became rough and the corrosion rate was maximally 0.1mm/3000hrs. And mass transfer from the high temperature to the lower temperature area was observed: crystals of Fe-Cr were found on the tube surface in low-temperature part. The size of crystal was 0.1 
0.2 mm. The depositing crystal was ferrite grain and the chemical composition ratio (mass%) of Fe to Cr was 9:1.
Kikuchi, Kenji; Kogawa, Hiroyuki; Futakawa, Masatoshi; Ishikura, Shuichi*; Kaminaga, Masanori; Hino, Ryutaro
Journal of Nuclear Materials, 318(1-3), p.84 - 91, 2003/05
Times Cited Count：16 Percentile：71.11(Materials Science, Multidisciplinary)In mercury spallation target development pitting is a technical issue, which is appeared on the target vessel in conjunction with the pressure wave. Pitting is found in the off-beam line test by Split Hopkinson Pressure Bar (SHPB) test and then found in the on-beam test of mercury target at WNR of LANSCE. In SHPB tests pressure in mercury was reduced from 80, 40, 20 and 10MPa. And type 316 stainless steel was inspected before and after the impacting test at x450 magnification. Results show that over 20MPa pitting was generated. But at the lowest pressure in mercury, the number of pitting was very limited and substantial damage was small. Substantial damage by pitting is characterized by holes because mass will be removed from the wall. Depression itself may not be a substantial damage as long as it is not accompanied with holes.
Kikuchi, Kenji; Kurata, Yuji; Saito, Shigeru; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Miura, Kuniaki*
Nihon Kikai Gakkai 2002-Nendo Nenji Taikai Koen Rombunshu, p.273 - 274, 2002/09
Corrosion-erosion properties of type 316 austenitic stainless steel were investigated at 450oC. The study aims at developing ADS, accelerator driven system, for nuclear transmutation of long lived activated nuclei to shorter ones. After 3000 hrs flow of eutectic 45Pb-55Bi loop tubes were cut and analyzed by optical microscope, SEM, EDX, WDX and TEM. It is concluded that corrosion-erosion depth is maximally 0.1mm per 3000 hrs and Cr-Fe crystals were precipitated in the lower temperature of flowing channel. Further more inspection results of Electro Magnetic Pump, Electro Magnetic Flow meter and controlling valve were also reported. Output signal from EMF was stable after certain time duration. In this experiment oxygen content in Pb-Bi was not actively controlled but Pb-Bi was covered by 4N Argon gas.
Von-Moellendorff, U.*; Maekawa, Fujio; Giese, H.*; Wilson, P. P. H.*
Fusion Engineering and Design, 51-52(Part.B), p.919 - 924, 2000/11
Times Cited Count：4 Percentile：32.52(Nuclear Science & Technology)no abstracts in English
Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Wada, Masayuki*; Maekawa, Hiroshi
Fusion Technology, 34(1), p.6 - 17, 1998/08
no abstracts in English
Hatano, Toshihisa; ; ; *; *; Kitamura, Kazunori*; Kuroda, Toshimasa*; Akiba, Masato; Takatsu, Hideyuki
Fusion Engineering and Design, 39-40, p.363 - 370, 1998/00
Times Cited Count：20 Percentile：81.49(Nuclear Science & Technology)no abstracts in English
Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Uno, Yoshitomo; Wada, Masayuki*; Maekawa, Hiroshi; Ikeda, Yujiro; Takeuchi, Hiroshi
Fusion Technology 1998, 2, p.1263 - 1266, 1998/00
no abstracts in English
Maekawa, Fujio; Konno, Chikara; Oyama, Yukio; Ikeda, Yujiro; Wada, Masayuki*; Uno, Yoshitomo; Y.M.Verzilov*; Maekawa, Hiroshi
Fusion Technology, 30(3(PT.2B)), p.1081 - 1087, 1996/12
no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi; Oyamada, Rokuro
Journal of Nuclear Materials, 233-237(PT.A), p.218 - 223, 1996/00
Times Cited Count：9 Percentile：62.07(Materials Science, Multidisciplinary)no abstracts in English
Maekawa, Fujio; Konno, Chikara; Wada, Masayuki*; Oyama, Yukio; Ikeda, Yujiro; Uno, Yoshitomo; Verzilov, Y.*; Maekawa, Hiroshi
JAERI-Research 95-018, 112 Pages, 1995/03
JAERI-Research-95-018.pdf:4.45MB
no abstracts in English
Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Uno, Yoshitomo; Verzilov, Y.*; Wada, Masayuki*; Maekawa, Hiroshi
JAERI-Research 95-017, 71 Pages, 1995/03
JAERI-Research-95-017.pdf:3.09MB
no abstracts in English
Ikeda, Yujiro; Konno, Chikara; Maekawa, Fujio; Uno, Yoshitomo; Oyama, Yukio; Kosako, Kazuaki*; Maekawa, Hiroshi
Fusion Engineering and Design, 28, p.449 - 456, 1995/00
no abstracts in English
Maekawa, Fujio; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi
JAERI-Research 94-044, 143 Pages, 1994/12
JAERI-Research-94-044.pdf:5.16MB
no abstracts in English
Konno, Chikara; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro; Kosako, Kazuaki*; Maekawa, Hiroshi
JAERI-Research 94-043, 96 Pages, 1994/12
JAERI-Research-94-043.pdf:3.5MB
no abstracts in English
Konno, Chikara; Maekawa, Fujio; *; Kosako, Kazuaki*; Ikeda, Yujiro; Oyama, Yukio; Maekawa, Hiroshi
JAERI-Tech 94-019, 43 Pages, 1994/10
no abstracts in English
Maekawa, Hiroshi
Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.15 - 24, 1994/00
no abstracts in English
Maekawa, Fujio; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Ikeda, Yujiro; Maekawa, Hiroshi
Fusion Technology, 21(3), p.2107 - 2111, 1992/05
no abstracts in English
