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Search Results: Records 1-20 displayed on this page of 160

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Journal Articles

Study on premixing phase of steam explosion at JAERI

; Moriyama, Kiyofumi; Maruyama, Yu; H.Park*; Y.Yang*; Sugimoto, Jun

Nucl. Eng. Des., 189(1-3), p.205 - 221, 1999/00

https://doi.org/10.1016/S0029-5493(98)00273-8
 Times Cited Count：6 Percentile：44.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical evaluation of interfacial area concentration using the immiscible lattice gas

Watanabe, Tadashi; Ebihara, Kenishi

Nucl. Eng. Des., 188(1), p.111 - 121, 1999/00

https://doi.org/10.1016/S0029-5493(99)00020-5
 Times Cited Count：6 Percentile：44.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical heat flux at high velocity channel flow with high subcooling

Sudo, Yukio; Kaminaga, Masanori

Nucl. Eng. Des., 187, p.215 - 227, 1999/00

https://doi.org/10.1016/S0029-5493(98)00294-5
 Times Cited Count：8 Percentile：52.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Simulation studies of plasma initiation and disruption in JT-60U

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; Matsukawa, Makoto; Ushigusa, Kenkichi

Nucl. Eng. Des., 45(1), p.15 - 29, 1999/00

no abstracts in English

Journal Articles

Visualization study of molten metal-water interaction by using neutron radiography

Mishima, Kaichiro*; Hibiki, Takashi*; Saito, Y.*; Sugimoto, Jun; Moriyama, Kiyofumi

Nucl. Eng. Des., 189(1-3), p.391 - 403, 1999/00

https://doi.org/10.1016/S0029-5493(98)00263-5
 Times Cited Count：13 Percentile：67.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study on in-vessel debris coolability in ALPHA program

Maruyama, Yu; ; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Y.Yang*; Sugimoto, Jun

Nucl. Eng. Des., 187(2), p.241 - 254, 1999/00

https://doi.org/10.1016/S0029-5493(98)00278-7
 Times Cited Count：20 Percentile：79.30(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Air vent in water chamber and surface coating on liner slides concerning auxiliary cooling system for the high temperature engineering test reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; Okubo, Minoru;

Nucl. Eng. Des., 185(2-3), p.229 - 240, 1998/00

https://doi.org/10.1016/S0029-5493(98)00287-8
 Times Cited Count：13 Percentile：70.38(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Simultaneous measurement of liquid velocity and interface profiles of horizontal duct wavy flow by ultrasonic velocity profile meter

Nakamura, Hideo; ; Kukita, Yutaka*

Nucl. Eng. Des., 184(2-3), p.339 - 348, 1998/00

https://doi.org/10.1016/S0029-5493(98)00207-6
 Times Cited Count：9 Percentile：59.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics of a next-generation reactor relying on steam generator secondary side cooling for primary depressurization and long-term passive core cooling

Yonomoto, Taisuke; ; Anoda, Yoshinari

Nucl. Eng. Des., 185(1), p.83 - 96, 1998/00

https://doi.org/10.1016/S0029-5493(98)00231-3
 Times Cited Count：3 Percentile：31.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Influence of thermal properties of zirconia shroud on analysis of PHEBUS FPTO bundle degradation test with ICARE2 code

Hidaka, Akihide; Nakamura, Jinichi; Sugimoto, Jun

Nucl. Eng. Des., 168(1-3), p.361 - 371, 1997/00

https://doi.org/10.1016/S0029-5493(96)00009-X
 Times Cited Count：2 Percentile：22.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Feasibility study on the applicability of a diffusion-welded compact intermediate heat exchanger to next-generation high temperature gas-cooled reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; ;

Nucl. Eng. Des., 168, p.11 - 21, 1997/00

https://doi.org/10.1016/S0029-5493(96)01361-1
 Times Cited Count：49 Percentile：94.13(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Integrity assessment of the high temperature engineering test reactor(HTTR) control rod at very high temperatures

Tachibana, Yukio; Shiozawa, Shusaku; ; ;

Nucl. Eng. Des., 172(1-2), p.93 - 102, 1997/00

https://doi.org/10.1016/S0029-5493(97)00030-7
 Times Cited Count：8 Percentile：55.80(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The HTTR reactor pressure vessel and its integrity against a PTS event

Kurihara, Ryoichi

Nucl. Eng. Des., 172(3), p.317 - 325, 1997/00

https://doi.org/10.1016/S0029-5493(97)00082-4
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Probabilistic fracture mechanics analyses of nuclear pressure vessels under PTS events

Yagawa, Genki*; Yoshimura, Shinobu*; ; Hirano, Masashi

Nucl. Eng. Des., 174(1), p.91 - 100, 1997/00

https://doi.org/10.1016/S0029-5493(97)00072-1
 Times Cited Count：9 Percentile：59.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress of LWR structural safety research at JAERI

Shibata, Katsuyuki

Nucl. Eng. Des., 174(1), p.79 - 90, 1997/00

https://doi.org/10.1016/S0029-5493(97)00071-X
 Times Cited Count：1 Percentile：14.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Passive heat removal by vessel cooling system of HTTR during no forced cooling accidents

Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Shinozaki, Masayuki

Nucl. Eng. Des., 166(2), p.179 - 190, 1996/00

https://doi.org/10.1016/0029-5493(96)01268-X
 Times Cited Count：22 Percentile：84.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical prediction of augmented turbulent heat transfer in an annular fuel channel with repeated two-dimensional square ribs

Takase, Kazuyuki

Nucl. Eng. Des., 165, p.225 - 237, 1996/00

https://doi.org/10.1016/0029-5493(95)01153-6
 Times Cited Count：9 Percentile：61.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of aseismic integrity in the HTTR core-bottom structure,V; On the static and dynamic behavior of graphitic HTTR key-keyway structures

Futakawa, Masatoshi; Takada, Shoji; ; Iyoku, Tatsuo

Nucl. Eng. Des., 166, p.47 - 54, 1996/00

https://doi.org/10.1016/0029-5493(96)01242-3
 Times Cited Count：4 Percentile：38.96(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of time-dependent boundary-fitted curvilinear coordinate system for kinetic analysis of aqueous fuel solution sloshing behaviour

Yamamoto, Toshihiro

Nucl. Eng. Des., 154(2), p.145 - 155, 1995/03

https://doi.org/10.1016/0029-5493(94)00914-K
 Times Cited Count：1 Percentile：17.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Generating material strength standards of aluminum alloys for research reactors, II; Design fatigue curve under non-effective creep condition

Tsuji, Hirokazu; Miya, Kenzo*

Nucl. Eng. Des., 155, p.547 - 557, 1995/00

https://doi.org/10.1016/0029-5493(94)00928-R
 Times Cited Count：2 Percentile：27.03(Nuclear Science & Technology)

no abstracts in English

160 (Records 1-20 displayed on this page)