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Journal Articles

Comparison of two-phase critical flow models for estimation of leak flow rate through cracks

Watanabe, Tadashi*; Katsuyama, Jinya; Mano, Akihiro

International Journal of Nuclear and Quantum Engineering (Internet), 13(11), p.516 - 519, 2019/10

The estimation of leak flow rates through narrow cracks in structures is of importance for nuclear reactor safety, since the leak flow could be detected before occurrence of loss-of-coolant accidents. The two-phase critical leak flow rates are calculated using the system analysis code, and two representative non-homogeneous critical flow models, Henry-Fauske model and Ransom-Trapp model, are compared. The pressure decrease and vapor generation in the crack, and the leak flow rates are found to be larger for the Henry-Fauske model. It is shown that the leak flow rates are not affected by the structural temperature, but affected largely by the roughness of crack surface.

Journal Articles

Flow-accelerated corrosion of type 316L stainless steel caused by turbulent lead-bismuth eutectic flow

Wan, T.; Saito, Shigeru

Metals, 8(8), p.627_1 - 627_22, 2018/08

 Times Cited Count:5 Percentile:43.06(Materials Science, Multidisciplinary)

Journal Articles

Research and development on lead-bismuth technology for accelerator-driven transmutation system at JAERI

Kurata, Yuji; Kikuchi, Kenji; Saito, Shigeru; Kamata, Kinya*; Kitano, Teruaki*; Oigawa, Hiroyuki

Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.267 - 277, 2004/05

R&D on lead-bismuth technology have been conducted for accelerator driven system. From the test results of 316SS using JLBL-1 for 3000h without active oxygen control, mass transfer from high temperature to low temperature parts was observed. It was found that deposition of Pb/Bi and Fe-Cr grains in the annular channel of the electro-magnetic pump caused plugging and decrease in flow rate. The modification of the loop system brought about a good effect on operation. Significant erosion/corrosion was not observed in the experiment using MES loop for 1000h under 10$$^{-5}$$wt.% oxygen condition. The results of static corrosion tests showed the following: corrosion depth decreased at 450$$^{circ}$$C with increasing Cr content in steels while corrosion depth of JPCA and 316SS became larger due to ferritization caused by dissolution of Ni and Cr at 550$$^{circ}$$C. Si-added steel exhibited good corrosion resistance at 550$$^{circ}$$C.

Journal Articles

Water flow experiments and analyses on the cross-flow type mercury target with perforated plates

Haga, Katsuhiro; Kinoshita, Hidetaka; Kaminaga, Masanori; Hino, Ryutaro; Tagawa, Hisato*; Kukita, Yutaka*

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 8 Pages, 2003/04

The cross-flow type mercury target, in which mercury flows crossing the proton beam path, has been developed as the spallation target of the material and life science facility in the high intensity proton accelerator project. As a part of design optimization, we proposed a mercury target using perforated plates aiming to simplify the inner structure, to make the target assembling easier, and to decrease the assembling cost. Then, the effectiveness of the target structure was investigated by no-heat water experiments and computational analyses. A mockup model of the cross-flow type mercury target using perforated plates was fabricated with plexi-glass and the water flow field was measured using PIV technique and the results were compared with the analytical results. The cross-flow field was realized by perforated plates and the analytical results corresponded well with the experimental results in the proton beam path where the cooling of heat generation is important.

JAEA Reports

Flow resistance of orifices and spacers of BWR thermal-hydraulic and neutronic coupling loop

Iguchi, Tadashi; Asaka, Hideaki; Nakamura, Hideo

JAERI-Research 2002-006, 152 Pages, 2002/03

JAERI-Research-2002-006.pdf:5.52MB

no abstracts in English

Journal Articles

Supercritical helium pump

Kato, Takashi

Tabo Kikai, 28(9), p.536 - 545, 2000/09

no abstracts in English

Journal Articles

Visualization of simulated molten-fuel behavior in a pressure vessel lower head using high-frame-rate neutron radiography

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka*; Mishima, Kaichiro*; Hibiki, Takashi*

Nuclear Technology, 125(2), p.213 - 224, 1999/02

 Times Cited Count:8 Percentile:55.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The Review of the application of neutron radiography to thermal hydraulic research

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Yasushi*; Nakamura, Hideo; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 424(1), p.66 - 72, 1999/00

 Times Cited Count:18 Percentile:77.12(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Experimental analysis for 3-D flow in lower plenum by flow visualization

Kunii, Katsuhiko

Flow Visualization and Image Processing 1997, Vol.2, p.592 - 597, 1997/02

no abstracts in English

Journal Articles

High-frame rate neutron radioscopy with a steady thermal neutron beam

Mishima, Kaichiro*; Hibiki, Takashi*; Fujine, Shigenori*; Yoneda, Kenji*; Kanda, Keiji*; Nishihara, Hideaki*; Matsubayashi, Masahito; Tsuruno, Akira

Fifth World Conf. on Neutron Radiography, 0, p.140 - 147, 1996/00

no abstracts in English

Journal Articles

Application of high-frame-rate neutron radiography with a steady thermal neutron beam to two-phase flow measurements in a metallic rectangular duct

Hibiki, Takashi*; Mishima, Kaichiro*; Matsubayashi, Masahito

Nuclear Technology, 110, p.422 - 435, 1995/06

 Times Cited Count:18 Percentile:84.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of local void fraction distribution in rod bundle under high-pressure high-temperature boil-off conditions by using optical void probe

Kumamaru, Hiroshige; Murata, Hideo; ; Kukita, Yutaka

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.217 - 222, 1995/00

no abstracts in English

Journal Articles

Evaluation of core thermal and hydraulic characteristics of HTTR

Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Murakami, Tomoyuki*; Fujii, Sadao*

Nucl. Eng. Des., 152, p.183 - 196, 1994/00

 Times Cited Count:11 Percentile:70

no abstracts in English

Journal Articles

Visualization of fluid phenomena using a high frame-rate neutron radiography with a steady thermal neutron beam

Hibiki, Takashi*; Mishima, Kaichiro*; Yoneda, Kenji*; Fujine, Shigenori*; Tsuruno, Akira; Matsubayashi, Masahito

Nuclear Instruments and Methods in Physics Research A, 351, p.423 - 436, 1994/00

 Times Cited Count:35 Percentile:93(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Experimental studies on thermal and hydraulic performance of fuel stack of VHTR, VI; Results of crossflow test by HENDEL multi-channel test rig

Takase, Kazuyuki; Hino, Ryutaro;

Nihon Genshiryoku Gakkai-Shi, 33(6), p.564 - 573, 1991/06

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Flow regime transitions in high-pressure steam-water horizontal pipe two-phase flow

Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka

ANS Proc. 1991 National Heat Transfer Conf., Vol. 5, p.269 - 276, 1991/00

no abstracts in English

Journal Articles

Effect of liquid flow rate on film boiling heat transfer during reflood in rod bundle

Onuki, Akira; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 27(6), p.535 - 546, 1990/06

no abstracts in English

JAEA Reports

Development of leak analysis programs from through-wall crack

; Shibata, Katsuyuki; Isozaki, Toshikuni

JAERI-M 90-050, 106 Pages, 1990/03

JAERI-M-90-050.pdf:2.17MB

no abstracts in English

37 (Records 1-20 displayed on this page)