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Journal Articles

Safety activities in JAERI related to ITER

Ohira, Shigeru; Tada, Eisuke; Hada, Kazuhiko; Neyatani, Yuzuru; Maruo, Takeshi; Hashimoto, Masayoshi*; Araki, Takao*; Nomoto, Kazuhiro*; Tsuru, Daigo; Ishida, Toshikatsu*; et al.

Fusion Engineering and Design, 54(3-4), p.515 - 522, 2001/04

https://doi.org/10.1016/S0920-3796(00)00580-9
 Times Cited Count：3 Percentile：27.1(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Three-dimensional numerical simulations of dust mobilization and air ingress characteristics in a fusion reactor during a LOVA event

Takase, Kazuyuki

Fusion Engineering and Design, 54(3-4), p.605 - 615, 2001/04

https://doi.org/10.1016/S0920-3796(00)00573-1
 Times Cited Count：12 Percentile：64.73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical simulations on dust-air two-phase flows in fusion experimental reactors during loss-of-vacuum-accident events

Takase, Kazuyuki

Fusion Technology, 39(2-Part.2), p.1043 - 1049, 2001/03

no abstracts in English

Journal Articles

Numerical analyses on heat transfer behavior in fusion reactors at accident events; Visualization of thermal-hydraulic phenomena at ICE and LOVA events

Takase, Kazuyuki; Ose, Yasuo*; Kume, Etsuo; Akimoto, Hajime

Kashika Joho Gakkai-Shi, 20(suppl.1), p.113 - 114, 2000/07

no abstracts in English

Journal Articles

Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki*; Seki, Yasushi; Akimoto, Hajime

Nuclear Fusion, 40(3Y), p.527 - 535, 2000/03

https://doi.org/10.1088/0029-5515/40/3Y/313
 Times Cited Count：11 Percentile：34.99(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Numerical analysis on ingress-of-coolant events in fusion reactors with TRAC-PF1 code

Ose, Yasuo*; Takase, Kazuyuki; Akimoto, Hajime

JAERI-Research 99-075, p.95 - 0, 2000/01

JAERI-Research-99-075.pdf:4.62MB

no abstracts in English

Journal Articles

Analyses of accident events on thermal-hydraulics in fusion reactor design

Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime

Nihon Kikai Gakkai Kansai Shibu Dai-75-ki Teiji Soukai Koenkai Koen Rombunshu, p.13_11 - 13_12, 2000/00

no abstracts in English

Journal Articles

Safety scenario and integrated thermofluid test

Seki, Yasushi; Kurihara, Ryoichi; Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Shibata, Mitsuhiko

Fusion Engineering and Design, 42(1-4), p.37 - 44, 1998/09

https://doi.org/10.1016/S0920-3796(98)00123-9
 Times Cited Count：1 Percentile：15.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Temperature distributions in a tokamak vacuum vessel of fusion reactor after the loss-of-vacuum events occurred

Takase, Kazuyuki; Kunugi, Tomoaki; ; Seki, Yasushi

Fusion Engineering and Design, 42, p.83 - 88, 1998/00

https://doi.org/10.1016/S0920-3796(97)00186-5
 Times Cited Count：13 Percentile：70.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present status of fusion safety experiments for thermal-hydraulics

Takase, Kazuyuki; Kunugi, Tomoaki

Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.781 - 785, 1997/08

https://ci.nii.ac.jp/naid/110003826910

no abstracts in English

Journal Articles

Visualization of exchange flows through breaches of a vacuum vessel in a fusion reactor under the LOVA condition

Takase, Kazuyuki; Kunugi, Tomoaki; Fujii, Sadao*; Shibazaki, Hiroaki*

Flow Visualization Image Process. 1997, 1(00), p.185 - 190, 1997/00

no abstracts in English

Journal Articles

Proposal of integrated test facility for in-vessel thermofluid safety of fusion reactors

Kurihara, Ryoichi; Seki, Yasushi; Ueda, Shuzo; Aoki, Isao; Nishio, Satoshi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Yamauchi, Michinori*; *; et al.

Journal of Fusion Energy, 16(3), p.225 - 230, 1997/00

https://doi.org/10.1023/A:1021895304522
 Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study on buoyancy-driven exchange flows through breaches of a tokamak vacuum vessel of a fusion reactor under the loss-of-vacuum-event condition

Takase, Kazuyuki; Kunugi, Tomoaki; Ogawa, Masuro; Seki, Yasushi

Nuclear Science and Engineering, 125(2), p.223 - 231, 1997/00

https://doi.org/10.13182/NSE97-A24269
 Times Cited Count：11 Percentile：65.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental and numerical studies on heat transfer and fluid flow characteristics in a vacuum vessel of fusion reactor after the loss-of-vacuum-events occurred

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Proc. of Int. Topical Meetig on Advanced Reactors Safety, 2, p.1268 - 1275, 1997/00

no abstracts in English

Journal Articles

Effects of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor

Takase, Kazuyuki; Kunugi, Tomoaki; Seki, Yasushi

Fusion Technology, 30(3(PT.2B)), p.1459 - 1464, 1996/12

no abstracts in English

JAEA Reports

Development of flow visualization technique for measurement of exchange flow rates under LOVA condition and results of the preliminary flow visualization experiment

Kunugi, Tomoaki; Takase, Kazuyuki; Ogawa, Masuro; Shibata, Mitsuhiko

JAERI-Tech 96-012, 91 Pages, 1996/03

JAERI-Tech-96-012.pdf:3.51MB

no abstracts in English

Journal Articles

Fusion safety experiments in JAERI

Kunugi, Tomoaki; Takase, Kazuyuki; Ogawa, Masuro; Seki, Yasushi

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.313 - 316, 1996/00

no abstracts in English

Journal Articles

Experimental study of buoyancy-driven exchange flow from breaches under LOVA condition

Takase, Kazuyuki; Kunugi, Tomoaki; Ogawa, Masuro; Seki, Yasushi

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.317 - 320, 1996/00

no abstracts in English

Journal Articles

A Preliminary experiment for a loss of vacuum events of fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki; Shibata, Mitsuhiko; Seki, Yasushi

Nihon Genshiryoku Gakkai-Shi, 38(11), p.904 - 906, 1996/00

https://doi.org/10.3327/jaesj.38.904
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation of tungsten temperature of divertor during Ex-LOCA and evaluation of corrosion depth of graphite during LOCA in fusion experimental reactor

Ogawa, Masuro; Takatsu, Hideyuki; Iida, Hiromasa; Seki, Yasushi

JAERI-M 91-119, 27 Pages, 1991/08

JAERI-M-91-119.pdf:1.0MB

no abstracts in English

20 (Records 1-20 displayed on this page)
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