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Zhang, H.*; Umehara, Yutaro*; Horiguchi, Naoki; Yoshida, Hiroyuki; Eto, Atsuro*; Mori, Shoji*
Energy, 335, p.138090_1 - 138090_18, 2025/10
Nuclear power is a key low-carbon energy source for a carbon-neutral future. In boiling water reactors (BWRs), steam-water annular flow near fuel rods is crucial for reactor safety, but its high-temperature, high-pressure conditions (285
C, 7 MPa) make direct measurement challenges. To address this, we used an HFC134a-ethanol system at lower conditions (40C, 0.7 MPa) to simulate BWR annular flow. Using a high-speed camera and the constant electric current method, we analyzed liquid-film characteristics, wave velocity and frequency. We also examined surface tension and interfacial shear stress effects. Furthermore, we proposed a new correlation for base film thickness.
Otani, Kyohei; Igarashi, Takahiro
Journal of the Electrochemical Society, 172(9), p.091503_1 - 091503_8, 2025/09
Times Cited Count：0 Percentile：0.00Zhang, H.*; Umehara, Yutaro*; Yoshida, Hiroyuki; Mori, Shoji*
International Journal of Heat and Mass Transfer, 211, p.124253_1 - 124253_13, 2023/09
Times Cited Count：13 Percentile：77.57(Thermodynamics)Zhang, H.*; Mori, Shoji*; Hisano, Tsutomu*; Yoshida, Hiroyuki
International Journal of Multiphase Flow, 159, p.104342_1 - 104342_15, 2023/02
Times Cited Count：13 Percentile：68.30(Mechanics)Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Akimoto, Hajime
Computational Fluid Dynamics 2004, p.649 - 654, 2006/00
no abstracts in English
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
C and 550CKurata, Yuji; Futakawa, Masatoshi; Saito, Shigeru
JAERI-Research 2005-002, 37 Pages, 2005/02
JAERI-Research-2005-002.pdf:20.04MB
Static corrosion tests of various austenitic and ferritic/martensitic steels were conducted in oxygen-saturated liquid Pb-Bi at 450C and 550C for 3000h to study the effects of temperature and alloying elements on corrosion behavior. Oxidation, grain boundary corrosion, dissolution and penetration were observed. The corrosion depth decreases at 450C with increasing Cr content in steels regardless of ferritic/martensitic or austenitic steels. Appreciable dissolution of Ni and Cr does not occur in the three austenitic steels at 450C. The corrosion depth of ferritic/martensitic steels also decreases at 550C with increasing Cr content whereas the corrosion depth of austenitic steels, JPCA and 316ss becomes larger due to ferritization caused by dissolution of Ni at 550C than that of ferritic/martensitic steels. An austenitic stainless steel containing about 5%Si exhibits fine corrosion resistance at 550C because the protective Si oxide film is formed and prevents dissolution of Ni and Cr.
Takase, Kazuyuki; Yoshida, Hiroyuki; Ose, Yasuo*; Tamai, Hidesada
JSME International Journal, Series B, 47(2), p.323 - 331, 2004/05
no abstracts in English
Kataoka, Isao*; Matsuura, Keizo*; Yoshida, Kenji*
JAERI-Tech 2002-015, 83 Pages, 2002/03
JAERI-Tech-2002-015.pdf:3.62MB
no abstracts in English
Mishima, Kaichiro*; Saito, Yasushi*
JAERI-Tech 2002-014, 83 Pages, 2002/03
JAERI-Tech-2002-014.pdf:6.83MB
no abstracts in English
Abe, Yutaka*
JAERI-Tech 2002-011, 70 Pages, 2002/03
JAERI-Tech-2002-011.pdf:5.62MB
no abstracts in English
Kurata, Yuji; Futakawa, Masatoshi; Kikuchi, Kenji; Saito, Shigeru; Osugi, Toshitaka
Journal of Nuclear Materials, 301(1), p.28 - 34, 2002/02
Times Cited Count：55 Percentile：93.78(Materials Science, Multidisciplinary)no abstracts in English
Kondo, Masaya; Nakamura, Hideo; Anoda, Yoshinari; Saishu, Sadanori*; Obata, Hiroyuki*; Shimada, Rumi*; Kawamura, Shinichi*
Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 9 Pages, 2002/00
no abstracts in English
Soyama, Kazuhiko; Metoki, Naoto; Minakawa, Nobuaki; ;
Hamon, 7(2), p.5 - 7, 1997/05
no abstracts in English
; Yagi, Junji*; Kumamaru, Hiroshige
JAERI-M 93-199, 48 Pages, 1993/10
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
Journal of Nuclear Science and Technology, 27(6), p.535 - 546, 1990/06
no abstracts in English
JAERI-M 86-135, 89 Pages, 1986/09
no abstracts in English
; ; J.R.Bartlit*; R.H.Sherman*
Fusion Technology, 10, p.137 - 148, 1986/00
no abstracts in English
Asahi, Yoshiro
Nucl.Eng.Des., 47(2), p.251 - 256, 1978/02
Times Cited Count：3no abstracts in English
Zhang, H.*; Umehara, Yutaro*; Mori, Shoji*; Horiguchi, Naoki; Yoshida, Hiroyuki
no journal, ,
Due to the operating conditions of BWRs (285C 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.
