Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
The Working Team for Examination of the Sample from Core Shrouds and Primary Loop Recirculation Pipi; Nakajima, Hajime*; Shibata, Katsuyuki; Tsukada, Takashi; Suzuki, Masahide; Kiuchi, Kiyoshi; Kaji, Yoshiyuki; Kikuchi, Masahiko; Ueno, Fumiyoshi; Nakano, Junichi; et al.
JAERI-Tech 2004-015, 114 Pages, 2004/03
JAERI-Tech-2004-015.pdf:38.06MB
The Tokyo Electric Power Company (TEPCO) visually inspected the weld joint of core shroud at Fukushima Dai-ni Nuclear Power Station Unit-2 by a direction of the Nuclear and Industrial Agency, cracks were observed at outer side of the ring weld joint (H3) between a core shroud middle trunk and a middle ring. TEPCO has conducted a material examination with Nippon Nuclear Fuel Development Co. Ltd. (NFD) on the specimen including cracks sampled from the core shroud. The present examination has been performed with the objective to independently investigate and evaluate the materials by jointly attending the examination with NFD from the planning stage. Based on results of the present examination, the probable presence of tensile residual stress by welding process and dissolved oxygen contents in the cooling water, it was shown that the cracks were considered to be stress corrosion cracking (SCC). However, the cause of the cracks needs more consideration on the way of shroud construction.
Nakano, Junichi; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Nemoto, Yoshiyuki; Tsuji, Hirokazu; Jitsukawa, Shiro
Journal of Nuclear Materials, 307-311(Part2), p.1568 - 1572, 2002/12
Times Cited Count：12 Percentile：60.73(Materials Science, Multidisciplinary)Type 316LN stainless steel of the international thermonuclear experimental reactor (ITER) Grade (316LN-IG SS) is being considered for the first wall/ blanket component. Hot isostatic pressing (HIP) technique is expected for the fabrication of module. To evaluate the integrity and susceptibility to stress corrosion cracking (SCC) of HIPed 316LN-IG SS, tensile tests in vacuum and slow strain rate tests (SSRT) in high temperature water were performed. Specimen with the HIPed joint shows no deterioration of the tensile strength and susceptibility to SCC in oxygenated water. Thermally sensitized specimen with the HIPed joint was low susceptible to SCC in creviced environment. It is concluded that the strength at joint location is as high as that at the base alloy and the joint interface appears integrity.
Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Yonekawa, Minoru; Nakano, Junichi; Tsuji, Hirokazu; Nakajima, Hajime
Journal of Nuclear Materials, 307-311(Part1), p.331 - 334, 2002/12
Times Cited Count：5 Percentile：34.51(Materials Science, Multidisciplinary)Irradiation assisted stress corrosion cracking (IASCC) caused by simultaneous effects of neutron irradiation and high temperature water environments has been pointed out as one of the major concerns of in-core structural materials not only for the light water reactors (LWRs) but also for the water-cooled fusion reactor. It is necessary to evaluate precisely stress condition under irradiation environment, because stress is one of key factors on IASCC. Stress relaxation of tensile type specimens under fast neutron irradiation at 288
C has been studied for type 316L stainless steel in Japan Materials Testing Reactor (JMTR). This paper describes the in-pile and out-of-pile stress-relaxation test results of tensile type specimens for type 316L stainless steel as compared with the literature data by Foster, which were mainly obtained by bent beam specimens. Moreover these experimental results were compared with the analytical ones by using Nakagawa's model.
Nemoto, Yoshiyuki; Miwa, Yukio; Kikuchi, Masahiko; Kaji, Yoshiyuki; Tsukada, Takashi; Tsuji, Hirokazu
Journal of Nuclear Science and Technology, 39(9), p.996 - 1001, 2002/09
Times Cited Count：6 Percentile：39.48(Nuclear Science & Technology)Surface morphology of oxidized stainless steel was evaluated using atomic force microscope (AFM) and scanning electron microscope (FE-SEM). Cross-sectional morphology of oxide layer on the specimens was evaluated using FE-SEM after fabrication. Focused ion beam (FIB) technique was applied to fabricate thin film samples of oxide films, which were used for microstructure observation by transmission electron microscope (FE-TEM), and microscopic chemical analysis by energy dispersed X-ray spectrometer (EDS). These preparations and observations were successful, and microstructure and chemical composition of oxide films were evaluated on nanometer scale. Effects of silicon (Si) doping and dissolved oxygen (DO) content in water for oxide layer formation are discussed.
Nemoto, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Tsuji, Hirokazu
JAERI-Tech 2001-079, 25 Pages, 2001/12
JAERI-Tech-2001-079.pdf:6.76MB
Development and research about analytical method for the study of oxide film on austenitic stainless steel had been conducted from the point of view for basic study of IASCC (Irradiation Assisted Stress Corrosion Cracking). Nickel plating and copper plating had been compared as the oxide film protection while the fabrication for cross sectional observation. And thin film specimens for microstructural observation were fabricated using FIB (Focused Ion Beam) technique. Microstructure of oxide film on stainless steel had been observed with FE-TEM (Field Emission gun - Transmission Electron Microscope), and the chemical composition was analyzed with EDS (Energy dispersed X-ray Spectrometer). The oxide film had been formed in high pressure (8MPa) and high temperature (288
) water, contains saturated oxygen. The thickness of oxide film was about 1
m as maximum. Micro grains of Fe oxide with 100nm in diameter were formed in the oxide film. On the boundary with alloy, there was about 10nm thickness of passive film formed with Cr oxide.
Akiyama, Kazuhiko; Zhao, Y.*; Sueki, Keisuke*; Tsukada, Kazuaki; Haba, Hiromitsu; Nagame, Yuichiro; Kodama, Takeshi*; Suzuki, Shinzo*; Otsuki, Tsutomu*; Sakaguchi, Masahiko*; et al.
Journal of the American Chemical Society, 123(1), p.181 - 182, 2001/01
Times Cited Count：66 Percentile：84.89(Chemistry, Multidisciplinary)no abstracts in English
*; Kiuchi, Kiyoshi;
JAERI-Research 96-020, 16 Pages, 1996/03
JAERI-Research-96-020.pdf:1.78MB
no abstracts in English
; ; Kiuchi, Kiyoshi
JAERI-Research 96-019, 20 Pages, 1996/03
JAERI-Research-96-019.pdf:1.37MB
no abstracts in English
Kiuchi, Kiyoshi; *; *;
Proc. of the Int. Symp. on Material Chemistry in Nuclear Environment, p.65 - 78, 1992/00
no abstracts in English
*; Kiuchi, Kiyoshi; ; *
Proc. of the Int. Symp. on Material Chemistry in Nuclear Environment, p.427 - 435, 1992/00
no abstracts in English
*; Kiuchi, Kiyoshi; *;
Proc. of the Int. Symp. on Material Chemistry in Nuclear Environment, p.469 - 477, 1992/00
no abstracts in English
Ogiwara, Norio; ; *; Sakamoto, Keishi; ; *; Ishizuka, H.*
Shinku, 35(3), p.392 - 394, 1992/00
no abstracts in English
Kiuchi, Kiyoshi; ; Kondo, Tatsuo
Journal of Nuclear Materials, 179-181, p.481 - 484, 1991/00
Times Cited Count：2 Percentile：31.86(Materials Science, Multidisciplinary)no abstracts in English
Kiuchi, Kiyoshi; ; H.Bolt*; Araki, Masanori; Seki, Masahiro
Journal of Nuclear Materials, 179-181, p.282 - 285, 1991/00
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)no abstracts in English
Kiuchi, Kiyoshi; ; Kondo, Tatsuo
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.177 - 188, 1988/00
no abstracts in English
Kiuchi, Kiyoshi; B.Harald*; ; Seki, Masahiro; Araki, Masanori
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku 29(2), p.189 - 197, 1988/00
no abstracts in English
; ; Shindo, Masami; ; ; ; ; ; *; *; et al.
JAERI-M 82-062, 23 Pages, 1982/06
no abstracts in English
; ; Kondo, Tatsuo
JAERI-M 82-052, 31 Pages, 1982/06
no abstracts in English
; Ogawa, Yutaka; ; Kondo, Tatsuo
JAERI-M 8807, 16 Pages, 1980/04
no abstracts in English
Ogawa, Yutaka; Shindo, Masami;
Journal of Nuclear Science and Technology, 16(1), p.62 - 71, 1979/00
Times Cited Count：0no abstracts in English
