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Obara, Kenjiro
Genshiryoku eye, 48(2), p.46 - 48, 2002/02
no abstracts in English
Obara, Kenjiro
Hoshasen To Sangyo, (92), p.56 - 60, 2001/12
no abstracts in English
; Hirakawa, Yasushi; Kano, Shigeki; Yoshida, Eiichi
PNC TN9410 98-048, 56 Pages, 1998/03
Planar specimens of functionally gradient material (FGM) for thermal stress relaxation in fast reactor environment were formed and evaluated. FGMs of AlO-SUS316L system and YO-SUS316L system were deposited on SUS316L substrates by low pressure plasma spraying. The deposited coatings with 6 layers in which the ratio of ceramics/SUS316FR changes from 0 to 100% by 20% were successfully formed. Cross-sectional observation of the coatings showed no cracks and the hardness in the coating increased continuously from the substrate to the surface. From the results of X-ray diffraction, there were no changes in the structure of SUS316L and YO between the powder and the coating. On the contrary, in the case of AlO, - AlO phase was detected in the coating formed from __$ powder. The specimens were exposed in liquid sodium at 823K or 923K for 3.6Ms(1000h). The coatings were damaged with many cracks in liquid sodium. It was revealed that the bonding strength between the sprayed particles were not sufficient. To improve the stability in liquid sodium, another specimens were formed with changing the chamber pressure during deposition. From the microstructural inspections of the specimens, the coating formed at higher chamber pressure showed less porosity.
; Kano, Shigeki; ; Tachi, Yoshiaki; Hirakawa, Yasushi; Yoshida, Eiichi
PNC TN9410 98-021, 68 Pages, 1998/02
Engineering ceramics have excellent properties such as high strength, high hardness and high heat resistance compared with metallic matelials. To apply the ceramic in fast reactor environment, it is necessary to evaluate the sodium compatibility and the influence of sodium on the mechanical properties of ceramics. In this study, the influence of high temperature sodium on the mechanical properties of sintered ceramics of conventional and high purity AlO, SiC, SiAlON, AlN and unidirectional solidified ceramics of AlO/YAG eutectic composite were investigated by means of flexure tests. Test specimens were exposed in liquid sodium at 823K and 923K for 3.6Ms. There were no changes in the flexural strength of the conventional and high purity AlO, AlN and AlO/YAG eutectic composite after the sodium exposure at 823K. On the contrary, the decrease in the flexural strength was observed in SiC and SiAlON. After the sodium exposure at 923K, there were also no changes in the flexural strength of AlN and AlO/YAG eutectic composite. In the conventional and high purity AlO and SiC, the flexural strength decreased and signs of grain boundary corrosion were detected by surface observation. The flexural strength of SiAlON after the sodium exposure at 923K increased instead of severe corrosion. In the specimens those showed no changes in the flexural strength, further exposure in sodium is needed to verify whether the mechanical properties degrade or not. For SiAlON, it is necessary to clarify the reason for the increased strength after the sodium exposure at 923K.
*; Katano, Yoshio; Noda, Kenji
Journal of Nuclear Materials, 258-263, p.1831 - 1835, 1998/00
Times Cited Count:1 Percentile:15.03(Materials Science, Multidisciplinary)no abstracts in English
Katano, Yoshio; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji
Journal of Nuclear Materials, 258-263, p.1842 - 1847, 1998/00
Times Cited Count:6 Percentile:49.22(Materials Science, Multidisciplinary)no abstracts in English
Katano, Yoshio; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji; Yamamoto, Shunya
Nuclear Instruments and Methods in Physics Research A, 140(1-2), p.152 - 158, 1998/00
no abstracts in English
Katano, Yoshio; Hojo, Kiichi; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji
Nuclear Instruments and Methods in Physics Research B, 141(1-4), p.411 - 418, 1998/00
Times Cited Count:6 Percentile:49.22(Instruments & Instrumentation)no abstracts in English
Katano, Yoshio; ; Yamaki, Daiju; Noda, Kenji
Journal of Nuclear Materials, 233-237, p.1325 - 1331, 1996/00
Times Cited Count:7 Percentile:54.42(Materials Science, Multidisciplinary)no abstracts in English