Behavior of entrainment droplet formed by high velocity air jet flow in stagnant water

Akabane, Masaaki*; Horiki, Sachiyo*; Osakabe, Masahiro*; Koizumi, Yasuo; Uchibori, Akihiro; Ohno, Shuji; Ohshima, Hiroyuki

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

http://ci.nii.ac.jp/naid/110010046297

Behavior of liquid droplets in a high-velocity gaseous jet was experimentally investigated to provide validation data for the evaluation method of sodium-water reaction phenomenon. The visualization experiment on the entrained liquid droplets in the air jet submerged in a water pool was carried out. Filament-like wisps from the wavy gas-liquid interface were observed. The wisps were broken off and entrained into the air jet. The velocity of the entrained liquid droplets was estimated from an image processing. The axial velocity of the liquid droplets increased as the air inlet velocity increased. Acceleration behavior of the liquid droplets was also confirmed quantitatively.

Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF core-I forced feed tests

Iwamura, Takamichi; *; Sudo, Yukio; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; *; Murao, Yoshio

JAERI-M 91-093, 89 Pages, 1991/06

JAERI-M-91-093.pdf:1.87MB

no abstracts in English

Fuel elements and fuel cycle concepts of actinide burner reactors; Conceptual study of actinide burner reacotors, IV

Ogawa, Toru; Mukaiyama, Takehiko; Takano, Hideki; Takizuka, Takakazu; ; *

JAERI-M 89-123, 38 Pages, 1989/09

JAERI-M-89-123.pdf:1.25MB

no abstracts in English

Nuclear characteristic analysis of TRU burner reactors; Design study on TRU transmutation reactors, II

Takano, Hideki; Mukaiyama, Takehiko; Takizuka, Takakazu; Ogawa, Toru; ; *

JAERI-M 89-072, 74 Pages, 1989/06

JAERI-M-89-072.pdf:2.32MB

no abstracts in English

Thermal-hydraulic study of integrated steam generator in PWR

Journal of Nuclear Science and Technology, 26(2), p.286 - 294, 1989/02

https://doi.org/10.3327/jnst.26.286

no abstracts in English

Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF

Koizumi, Yasuo; ; Kumamaru, Hiroshige; ; Tasaka, Kanji; *

Journal of Nuclear Science and Technology, 25(9), p.690 - 703, 1988/09

https://doi.org/10.3327/jnst.25.690

no abstracts in English

The results of 5% small break LOCA tests and natural circulation tests at the ROSA-IV LSTF

Tasaka, Kanji; ; Koizumi, Yasuo; Osakabe, Masahiro;

Nucl.Eng.Des., 108(1-2), p.37 - 44, 1988/02

https://doi.org/10.1016/0029-5493(88)90054-4

no abstracts in English

Core liquid level depression due to manometric effect during PWR small break LOCA; Effect of core bypass

; Yonomoto, Taisuke; Kukita, Yutaka; Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 25(3), p.274 - 282, 1988/00

https://doi.org/10.3327/jnst.25.274

no abstracts in English

Annular flow transition model in channels of various shapes

; *; Tasaka, Kanji

Nihon Kikai Gakkai Rombunshu, B, 54(500), p.953 - 958, 1988/00

https://doi.org/10.1299/kikaib.54.953

no abstracts in English

Heat transfer and thermal-hydraulics of Westinghouse-type pressurized water reactor steam generator; Assessment of RELAP5/MOD2 code

Koizumi, Yasuo; Kumamaru, Hiroshige; *; *; Tasaka, Kanji

Thermal Hydraulics of Nuclear Steam Generators/Heat Exchangers HTD,Vol. 102, p.21 - 28, 1988/00

no abstracts in English