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Inoue, Toshihiko; Sekio, Yoshihiro; Watanabe, Hideo*
Materia, 58(2), P. 92, 2019/02
For the evaluation of irradiated segregation behavior, Austenite-based stainless steel for the fast reactor, during irradiation was evaluated by utilizing TIARA facility (Irradiate temperature: 600 
C, Dose: 100 dpa) was observed by analytical electron microscope (JEM-ARM20FC). As a result of observation, the large-size void is observed in irradiation area, and MX segregation (containing Niobium) is not observed. In un-irradiation area the MX segregation is observed. And it is observed conspicuously that Nickel is segregation on the void surface. By the latest high-performance TEM utilization, these phenomenon are able to visualize. It is expected for the clarification of the irradiation damage and mechanism of void swelling, by the analyzing these phenomenon utilization with the latest high-performance TEM utilization.
TiUchida, Munenori*; Ishitsuka, Etsuo; Kawamura, Hiroshi
Journal of Nuclear Materials, 307-311(Part1), p.653 - 656, 2002/12
Times Cited Count：29 Percentile：84.85(Materials Science, Multidisciplinary)BeTi has high melting point and good chemical stability and is expected as the advanced material for the neutron multiplier of DEMO-Reactor that requires higher temperature than 600C in a blanket. To evaluate the tritium inventory in the breeding blanket, tritium release experiment of the neutron irradiated BeTi irradiated with a total fast neutron fluence of about 4 x 10
n/cm
(E
1MeV) at 330, 400 and 500C, was carried out. It was clear that tritium could be released easier than beryllium, and the apparent diffusion coefficient of BeTi was about two orders larger than that of beryllium at 600
1100C. In addition to good tritium release property, the swelling calculated from the density change of the specimens up to 1100C in this test was smaller than that of beryllium.
Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*
Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.215 - 220, 1996/00
no abstracts in English
Hishinuma, Akimichi
Materia, 34(3), p.328 - 331, 1995/00
no abstracts in English
Bamba, Tsunetaka; ;
JAERI-M 92-008, 16 Pages, 1992/02
no abstracts in English
Jitsukawa, Shiro; Katano, Yoshio; *; F.A.Garner*
Effects of Radiation on Materials, p.1034 - 1050, 1992/00
no abstracts in English
Kiuchi, Kiyoshi; ; Hishinuma, Akimichi
Journal of Nuclear Materials, 179-181, p.477 - 480, 1991/00
Times Cited Count：2 Percentile：31.86(Materials Science, Multidisciplinary)no abstracts in English
; ;
Journal of Nuclear Materials, 151, p.63 - 71, 1987/00
Times Cited Count：10 Percentile：70.03(Materials Science, Multidisciplinary)no abstracts in English
; *; Minato, Akio; Tone, Tatsuzo
Nucl.Eng.Des./Fusion, 5, p.221 - 231, 1987/00
no abstracts in English
; ; Hamada, S.; ;
Journal of Nuclear Materials, 141-143, p.444 - 447, 1986/00
Times Cited Count：4 Percentile：48.02(Materials Science, Multidisciplinary)no abstracts in English
; Katano, Y.; Shiraishi, K.
Journal of Nuclear Science and Technology, 21(9), p.671 - 677, 1984/00
Times Cited Count：14 Percentile：79.2(Nuclear Science & Technology)no abstracts in English
;
Journal of Nuclear Science and Technology, 20(8), p.668 - 673, 1983/00
Times Cited Count：9 Percentile：71.22(Nuclear Science & Technology)no abstracts in English
; Katano, Y.; Shiraishi, K.
Journal of Nuclear Science and Technology, 15(9), p.690 - 696, 1978/09
Times Cited Count：7no abstracts in English
; Katano, Y.; Shiraishi, K.
Journal of Nuclear Science and Technology, 15(4), p.288 - 295, 1978/04
Times Cited Count：6no abstracts in English
; Katano, Y.; ; Shiraishi, K.
Journal of Nuclear Science and Technology, 13(11), p.656 - 662, 1976/11
Times Cited Count：8no abstracts in English
JAERI-M 5949, 29 Pages, 1975/01
no abstracts in English
; ;
Genshiryoku Kogyo, 19(11), p.59 - 62, 1973/11
no abstracts in English
Ando, Masami; Tanigawa, Hiroyasu; Kurotaki, Hironori
no journal, ,
Reduced activation ferritic/martensitic steel (RAFM) is the most promising candidate for the blanket structural material in DEMO fusion reactor. Void swelling behavior as well as mechanical properties change under high dose fusion neutron irradiation is very important issue on R&D of RAFM steels (F82H). The purposes of this study are to investigate the void swelling behavior with F82H IEA, Mod-3 and BA07 heats after multi-ion-irradiation and to confirm the peak swelling temperature. From results of microstructure observation for F82H Mod-3 and BA07 heats at 470C by multi-ion beam irradiation, cavities are observed from 0.8 to 1.2
m (damage level 20 dpa) from an irradiation surface at 470C irradiated specimen. On the other hand, few cavities are observed in same region at 400C irradiation. This result shows that a swelling peak temperature with F82H weldments by ion irradiation will be also around 470C.
