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Zablackaite, G.; Shiotsu, Hiroyuki; Kido, Kentaro; Sugiyama, Tomoyuki
Nuclear Engineering and Technology, 56(2), p.536 - 545, 2024/02
Times Cited Count：1 Percentile：62.55(Nuclear Science & Technology)Hirota, Noriaki; Nakano, Hiroko; Fujita, Yoshitaka; Takeuchi, Tomoaki; Tsuchiya, Kunihiko; Demura, Masahiko*; Kobayashi, Yoshinao*
The IV International Scientific Forum "Nuclear Science and Technologies"; AIP Conference Proceedings 3020, p.030007_1 - 030007_6, 2024/01
Dynamic strain aging (DSA) and intergranular stress corrosion cracking (intragranular SCC) occur in high temperature pressurized water simulating a boiling water reactor environment due to changes in dissolved oxygen (DO) content, respectively. In order to clearly understand the difference between these phenomena, the mechanism of their occurrence was summarized. As a result, it was found that DSA due to intragranular cracking occurred in SUS304 stainless steel at low DO 
1 ppb, while DSA was suppressed at DO 100 to 8500 ppb due to the formation of oxide films on the surface. On the other hand, when DO was increased to 20000 ppb, the film was peeled from the matrix, O element diffused to the grain boundary of the matrix, resulting in intergranular SCC. These results are indicated that the optimum DO concentration must be adjusted to suppress crack initiation due to DSA and intergranular SCC.
Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Akimoto, Hajime
Proceedings of 2005 ASME International Mechanical Engineering Congress and Exposition (CD-ROM), 8 Pages, 2005/11
no abstracts in English
Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada
JSME International Journal, Series B, 47(2), p.323 - 331, 2004/05
no abstracts in English
Yokoyama, Sumi; Noguchi, Hiroshi; Kinouchi, Nobuyuki; Yamamoto, Hideaki; Kato, Shohei; ;
Hoken Butsuri, 34(1), p.57 - 66, 1999/00
no abstracts in English
Ioka, Ikuo; Onuki, Kaoru; Futakawa, Masatoshi; Kuriki, Yoshiro*; ; Nakajima, Hayato; Shimizu, Saburo
Zairyo, 46(9), p.1041 - 1045, 1997/09
no abstracts in English
; ; ; ; Matsuzuru, Hideo
JAERI-M 89-200, 26 Pages, 1989/12
no abstracts in English
Osakabe, Masahiro; ;
JAERI-M 83-022, 26 Pages, 1983/02
no abstracts in English
Abe, Yutaka; Sudo, Yukio; Osakabe, Masahiro
Journal of Nuclear Science and Technology, 20(7), p.571 - 583, 1983/00
Times Cited Count：6 Percentile：60.58(Nuclear Science & Technology)no abstracts in English
;
JAERI-M 82-055, 51 Pages, 1982/06
no abstracts in English
;
JAERI-M 9755, 115 Pages, 1981/11
no abstracts in English
Zhang, H.*; Umehara, Yutaro*; Mori, Shoji*; Horiguchi, Naoki; Yoshida, Hiroyuki
no journal, ,
Due to the operating conditions of BWRs (285
C and 7 MPa), the direct visualization and detailed liquid film measurement of steam-water annular flow in BWRs have been highly challenging. This study addresses this limitation by developing a novel HFC134a-ethanol annular flow system at lower temperature and pressure (40C and 0.7 MPa), simulating the steam-water annular flow under BWR conditions. The experiments of HFC134a-ethanol upward annular flow were conducted in a 5 mm inner diameter tube using the constant electric current method, and we obtained the flow characteristics including base, average, and maximum film thickness and the height of disturbance wave.
