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Pokor, C.*; Herbelin, A.*; Couvant, T.*; Kaji, Yoshiyuki
NEA/NSC/R(2016)5 (Internet), p.317 - 360, 2017/05
In aged BWR plants, certain locations in the mid-plane of the core shroud experience fluence levels at which the materials become susceptible to irradiation assisted stress corrosion cracking (IASCC). BWRVIP (Boiling Water Reactor Vessel Internals Program) has developed crack growth disposition methodologies for evaluating intergranular stress corrosion cracking (IGSCC) in the internal components of BWRs and the Japan Nuclear Energy Safety organization (JNES) has been conducting a project related to IASCC crack growth rate data as a part of safety research and development study for the aging management and maintenance of the nuclear power plants. Although many investigators proposed prediction models for SCC and IASCC growth rates for austenitic stainless steels and Ni alloys, even more improvements of models are necessary as compared with the detailed experimental results, because these models are still preliminary models.
Ebihara, Kenichi; Kaburaki, Hideo; Itakura, Mitsuhiro
"Hagane No Kikaiteki Tokusei Ni Oyobosu Suiso No Koka To Sono Hyoka" Shimpojium Yokoshu (USB Flash Drive), 6 Pages, 2014/09
Since hydrogen(H) embrittlement is one factor causing degradation and/or fracture of steel, understanding its mechanism is required. The grain-boundary(GB) decohesion due to segregation of H is considered to cause the delayed fracture of high strength steels and the cold cracking in welding. In the model based on GB decohesion, information of strength of GBs estimated in the atomic scale is used for the estimation of strength or crack propagation in the macroscopic scale. However the modeling between the atomic and the macroscopic scales is not clear. In particular, the validity of the model using the elastic continuum around nano-cracks for stress concentration at the crack tip is not clear. Thus, we examined the difference of the stress distribution around the nano-crack which was estimated by molecular dynamics and by a continuum calculation. As a result, the discrepancy became remarkable at high strain. The stress concentration was not simulated by the elastic continuum model.
Onizawa, Kunio; Tsutsumi, Hideaki*; Suzuki, Masahide; Shibata, Katsuyuki; Ueno, Fumiyoshi; Kaji, Yoshiyuki; Tsukada, Takashi; Nakajima, Hajime*
JAERI-Tech 2003-073, 125 Pages, 2003/08
JAERI-Tech-2003-073.pdf:11.62MB
Concerning the cracks due to stress corrosion cracking (SCC) observed on the core shrouds of BWRs, a study was conducted on structural integrity evaluation based on crack growth analysis. The cracks investigated were those observed on the regions of lower ring and support ring of the core shroud at Kashiwazaki-Kariwa Nuclear Power Station (NPS) Unit-3, and that on the middle shell region of the core shroud at Fukushima Daiichi NPS Unit-4 of Tokyo Electric Power Company. It was confirmed through data analysis of past SCC growth rate experiments applicable to the condition of the ring regions that the SCC growth rate prescribed in the JSME rule was conservative. The analysis on the core shroud rigidity with a crack indicated that the rigidity reduction was small enough not to affect the dynamic seismic response for the regions studied. Through the comparison of the required area in a cracked section or the allowable crack length, and crack growth analysis results, it was confirmed that the integrity of the core shrouds would be maintained even 4 effective full power years later.
Li, Y.*; Kato, Daisuke*; Shibata, Katsuyuki; Onizawa, Kunio
Nihon Kikai Gakkai Rombunshu, A, 69(678), p.239 - 245, 2003/02
no abstracts in English
Shibata, Katsuyuki; Onizawa, Kunio; Kato, Daisuke*; Li, Y.*
Nihon Kikai Gakkai 2001-Nendo Nenji Taikai Koen Rombunshu, p.389 - 390, 2001/00
no abstracts in English
Kato, Daisuke*; Li, Y.*; Shibata, Katsuyuki; Onizawa, Kunio
Nihon Kikai Gakkai 2001-Nendo Nenji Taikai Koen Rombunshu, p.391 - 392, 2001/00
no abstracts in English
Hatano, Toshihisa; Goto, Masahiro*; Yamada, Tetsuji*; Nomura, Yuichiro*; Saito, Masakatsu*
Fusion Engineering and Design, 49-50, p.207 - 212, 2000/11
Times Cited Count：3 Percentile：26.4(Nuclear Science & Technology)no abstracts in English
Motooka, Takafumi; Kiuchi, Kiyoshi
Fushoku Boshoku Kyokai Dai-47-Kai Zairyo To Kankyo Toronkai Koenshu (C-207S), p.299 - 302, 2000/00
no abstracts in English
Hatano, Toshihisa; Kanari, Moriyasu*; Sato, Satoshi*; *; Furuya, Kazuyuki; Kuroda, Toshimasa*; *; Enoeda, Mikio; Takatsu, Hideyuki
Journal of Nuclear Materials, 258-263(PT.A), p.950 - 954, 1998/00
Times Cited Count：12 Percentile：68.65(Materials Science, Multidisciplinary)no abstracts in English
Shibata, Katsuyuki; Isozaki, Toshikuni; *
JAERI-Data/Code 95-015, 67 Pages, 1995/11
JAERI-Data-Code-95-015.pdf:1.77MB
no abstracts in English
Proc. of 12th Japan-Korea Seminar on Ceramics, 0, p.301 - 305, 1995/00
no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni; Oku, Tatsuo*
Tanso, 0(153), p.155 - 162, 1992/00
no abstracts in English
Ishiyama, Shintaro; Oku, Tatsuo*; Eto, Motokuni
Journal of Nuclear Science and Technology, 28(5), p.472 - 483, 1991/05
no abstracts in English
JAERI-M 90-089, 70 Pages, 1990/06
no abstracts in English
;
Nihon Genshiryoku Gakkai-Shi, 30(2), p.181 - 192, 1988/02
Times Cited Count：2 Percentile：31.31(Nuclear Science & Technology)no abstracts in English
; ;
Journal of Nuclear Science and Technology, 24(9), p.719 - 723, 1987/09
Times Cited Count：6 Percentile：55.64(Nuclear Science & Technology)no abstracts in English
; *; Yagawa, Motoki*
Nucl.Eng.Des., 68, p.71 - 85, 1987/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
; ;
Nihon Genshiryoku Gakkai-Shi, 28(10), p.966 - 971, 1986/10
Times Cited Count：3 Percentile：40.87(Nuclear Science & Technology)no abstracts in English
*;
Journal of Nuclear Materials, 137, p.124 - 129, 1986/00
Times Cited Count：11 Percentile：74.97(Materials Science, Multidisciplinary)no abstracts in English
; *; Yagawa, Motoki*
JAERI 1276, 70 Pages, 1982/03
no abstracts in English
