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JAEA Reports

Natural convection tests with the in-core structure test section (T$$_{2}$$) of the helium engineering demonstration loop (HENDEL)

Takada, Shoji; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Ioka, Ikuo; Sudo, Yukio

JAERI-Research 95-048, 41 Pages, 1995/07

JAERI-Research-95-048.pdf:1.22MB

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics inside in-core structure test section (T$$_{2}$$) of helium engineering demonstration loop (HENDEL) under loss of forced circulation condition

Takada, Shoji; Inagaki, Yoshiyuki; Ioka, Ikuo; Sudo, Yukio

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.1087 - 1092, 1995/00

no abstracts in English

JAEA Reports

Journal Articles

Leakage flow characteristics of seal mechanism for HTGR core support blocks

;

Journal of Nuclear Science and Technology, 24(9), p.742 - 747, 1987/09

 Times Cited Count:3 Percentile:38.12(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The effect of crossflow on flow distribution in HTGR core column

; Takizuka, Takakazu

Journal of Nuclear Science and Technology, 24(7), p.516 - 525, 1987/07

 Times Cited Count:8 Percentile:63.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Leakage flows in high-temperature gas-cooled reactor graphite fuel elements

; Takizuka, Takakazu

Journal of Nuclear Science and Technology, 22(5), p.387 - 397, 1985/00

 Times Cited Count:6 Percentile:64.59(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Leakage Flow of Gases through Gaps between Contacting Surfaces

; Takizuka, Takakazu;

JAERI-M 84-128, 19 Pages, 1984/07

JAERI-M-84-128.pdf:0.7MB

no abstracts in English

Journal Articles

Experiments on graphite block gaps in bottom-core structure of experimental very high-temperature gas-cooled reactor

; ; Takizuka, Takakazu; ; Sanokawa, Konomo

Nihon Genshiryoku Gakkai-Shi, 26(7), p.977 - 987, 1984/00

no abstracts in English

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