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Journal Articles

High Temperature Gas-cooled Reactor

Tanaka, Toshiyuki; Muto, Yasushi

Karyoku Genshiryoku Hatsuden, 51(10), p.318 - 323, 2000/10

no abstracts in English

Journal Articles

Fabrication of full-scale sector model for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; *; Takahashi, Hiroyuki*; Tada, Eisuke; Ioki, Kimihiro*; Johnson, G.*; Onozuka, Masanori*; Y.Utin*; Sonnazzaro, G.*; et al.

Proc. of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 2, p.933 - 936, 1998/00

no abstracts in English

JAEA Reports

After-service inspection of HENDEL in-core structure test section T$$_{2}$$; 1, Inspection results at dismantlement

Fujisaki, Katsuo; Inagaki, Yoshiyuki; ; ; ; ; Sekita, Kenji; Morisaki, Norihiro; *; Iwatsuki, Jin*; et al.

JAERI-Tech 97-053, 57 Pages, 1997/10

JAERI-Tech-97-053.pdf:3.26MB

no abstracts in English

JAEA Reports

Design of helium-gas supplying facility of out-of-pile demonstration test for HTTR heat utilization system

Hino, Ryutaro; Fujisaki, Katsuo; ; ; Ota, Yukimaru; ; ; ; ; ; et al.

JAERI-Tech 96-037, 45 Pages, 1996/09

JAERI-Tech-96-037.pdf:1.49MB

no abstracts in English

JAEA Reports

Summary of facility and operating experience on Heliu Engineering Demonstration Loop, HENDEL

; Fujisaki, Katsuo; ; ; Ota, Yukimaru; Watanabe, Shuji; Kobayashi, Hideki*;

JAERI-Tech 96-030, 244 Pages, 1996/07

JAERI-Tech-96-030.pdf:7.65MB

no abstracts in English

JAEA Reports

Critical review and discussion on HENDEL demonstration tests for HTTR heat utilization systems

Hino, Ryutaro; Suzuki, Kunihiro; ; ; Fukaya, Kiyoshi; Shimizu, Saburo; Onuki, Kaoru; Takada, Shoji; ; Sudo, Yukio

JAERI-Review 95-016, 115 Pages, 1995/10

JAERI-Review-95-016.pdf:3.5MB

no abstracts in English

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

JAEA Reports

Thermal analysis code for test of passive cooling system by helium engineering demonstration loop (HENDEL) in-core structure test section (T$$_{2}$$): THANPACST2

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

JAERI-Data/Code 95-005, 203 Pages, 1995/06

JAERI-Data-Code-95-005.pdf:4.7MB

no abstracts in English

JAEA Reports

Demonstration tests for HTGR fuel elements and core components with test sections in HENDEL

; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;

JAERI 1333, 196 Pages, 1995/03

JAERI-1333.pdf:8.65MB

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

Study of air vent design for inverted U-tube type heat exchanger

Takada, Shoji; Shibata, Mitsuhiko; ; Fujisaki, Katsuo; Ota, Yukimaru; ;

JAERI-M 94-013, 89 Pages, 1994/02

JAERI-M-94-013.pdf:2.77MB

no abstracts in English

Journal Articles

Cooling performance of helium-gas/water coolers in HENDEL

Inagaki, Yoshiyuki; Takada, Shoji; ; ; Ota, Yukimaru; Shimomura, Hiroaki;

Nucl. Eng. Des., 146, p.301 - 309, 1994/00

 Times Cited Count:5 Percentile:49.99

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics of coolant in the core bottom structure of the High-Temperature Engineering Test Reactor

Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Ioka, Ikuo*; *

Nuclear Technology, 99, p.90 - 103, 1992/07

 Times Cited Count:7 Percentile:40.36(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural integrity test of thermocouples for coolant temperature measurement in HTTR core outlet region

*; Inagaki, Yoshiyuki; ; Ioka, Ikuo*; ; *; *; *

Nippon Genshiryoku Gakkai-Shi, 34(1), p.59 - 62, 1992/01

 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal-hydraulic performance of augmented fuel rod with square ribs for HTTR

; Hino, Ryutaro; Takase, Kazuyuki

Transport Phenomena Science and Technology 1992, p.690 - 695, 1992/00

no abstracts in English

Journal Articles

Estimation of hot streak in core bottom structure of high temperature gas-cooled reactor; Thermal mixing test of coolant in core bottom structure of HENDEL

Inagaki, Yoshiyuki; Suzuki, Kunihiro; Ioka, Ikuo*; Kunitomi, Kazuhiko;

Nippon Kikai Gakkai Rombunshu, B, 57(542), p.3520 - 3525, 1991/10

no abstracts in English

Journal Articles

Reliability test on control rod driving mechanism of HTTR with HENDEL

Hino, Ryutaro; *;

Nippon Genshiryoku Gakkai-Shi, 33(7), p.685 - 694, 1991/07

no abstracts in English

JAEA Reports

Sealing performance test for main flange of pressure vessel of T$$_{2}$$ test section in HENDEL

Ioka, Ikuo; *; Inagaki, Yoshiyuki; *; ; Suzuki, Kunihiro;

JAERI-M 90-221, 21 Pages, 1990/12

JAERI-M-90-221.pdf:0.68MB

no abstracts in English

Journal Articles

Thermal and hydraulic tests of test sections in helium engineering demonstration loop

; Suzuki, Kunihiro; Hino, Ryutaro; Takase, Kazuyuki; Inagaki, Yoshiyuki; Ioka, Ikuo

Nucl. Eng. Des., 120, p.435 - 445, 1990/00

 Times Cited Count:3 Percentile:57.82

no abstracts in English

Journal Articles

Application and experience of distributed control systems and coupled computer network in HTGR development facility

Shimomura, Hiroaki; Kawaji, Satoshi

Proc. of the IAEA Specialists' Meeting on Communication and Data Transfer in NPP, 17 Pages, 1990/00

no abstracts in English

33 (Records 1-20 displayed on this page)