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Journal Articles

Pool-boiling/bubbling void fraction in an annular flow channel

*; Kumamaru, Hiroshige; *; *; Tasaka, Kanji

Nucl. Eng. Des., 132, p.381 - 391, 1992/00

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

no abstracts in English

Journal Articles

Improvement of TRAC-PFl interfacial drag model for analysis of high-pressure horizontally-stratified two-phase flow

; Kukita, Yutaka; Anoda, Yoshinari; Nakamura, Hideo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 28(1), p.33 - 44, 1991/01

no abstracts in English

JAEA Reports

JNDC nuclear data library of fission products; Second version

Tasaka, Kanji; Katakura, Junichi; Ihara, Hitoshi; Yoshida, Tadashi*; Iijima, Shungo*; Nakashima, Ryuzo*; Nakagawa, Tsuneo; Takano, Hideki

JAERI 1320, 253 Pages, 1990/09

JAERI-1320.pdf:10.61MB

no abstracts in English

JAEA Reports

Developmental assessment of RELAP5/MOD3 code against ROSA-IV/TPTF horizontal two-phase flow experiments

Kukita, Yutaka; ; *; Anoda, Yoshinari; ; ; Tasaka, Kanji

JAERI-M 90-053, 22 Pages, 1990/03

JAERI-M-90-053.pdf:0.6MB

no abstracts in English

JAEA Reports

Effects of high temperature ECC injection on small and large break BWR LOCA simulation tests in ROSA-III program; RUNs 940 and 941

Suzuki, Mitsuhiro; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; Yonomoto, Taisuke; Murata, Hideo; Tasaka, Kanji

JAERI-M 90-051, 256 Pages, 1990/03

JAERI-M-90-051.pdf:6.41MB

no abstracts in English

Journal Articles

Critical heat flux for annulus under high-pressure, low-flow and mixed inlet conditions

Kumamaru, Hiroshige; Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 27(1), p.68 - 80, 1990/01

no abstracts in English

Journal Articles

Results of 0.5% cold-leg small-break LOCA experiments at ROSA-IV/LSTF; Effect of break orientation

; Kukita, Yutaka; Yonomoto, Taisuke; Koizumi, Yasuo; Tasaka, Kanji

Experimental Thermal and Fluid Science, 3, p.588 - 596, 1990/00

 Times Cited Count:18 Percentile:77.86(Thermodynamics)

no abstracts in English

Journal Articles

High pressure reflooding experiments of multi-rod bundle at ROSA-IV TPTF

Koizumi, Yasuo; Anoda, Yoshinari; Kumamaru, Hiroshige; Yonomoto, Taisuke; Tasaka, Kanji

Nucl. Eng. Des., 120, p.301 - 310, 1990/00

 Times Cited Count:4 Percentile:47.93(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Pressurized water reactor core instrument tube rupture; Experimental simulation at the ROSA-IV LSTF

Kukita, Yutaka; ; Nakamura, Hideo; Tasaka, Kanji

Nucl. Eng. Des., 120, p.249 - 257, 1990/00

 Times Cited Count:1 Percentile:20.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The Effects of break location on PWR small-break LOCA; Experimental study at the ROSA-IV LSTF

Kukita, Yutaka; Tasaka, Kanji; ; Yonomoto, Taisuke; Kumamaru, Hiroshige

Nucl. Eng. Des., 122, p.255 - 262, 1990/00

 Times Cited Count:20 Percentile:85.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Loop seal clearing and refilling during a PWR small-break LOCA

Kukita, Yutaka; Katayama, Jiro; Nakamura, Hideo; Tasaka, Kanji

Nucl. Eng. Des., 121, p.431 - 440, 1990/00

 Times Cited Count:11 Percentile:73.06(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reflood experiments in single rod channel under high-pressure condition

G.Xu*; Kumamaru, Hiroshige; Tasaka, Kanji

JAERI-M 89-178, 35 Pages, 1989/11

JAERI-M-89-178.pdf:0.74MB

no abstracts in English

Journal Articles

Temporary core liquid level depression during cold-leg small-break LOCA; Effect of break size and power level

Koizumi, Yasuo; Kumamaru, Hiroshige; *; Kukita, Yutaka; Tasaka, Kanji

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.12 - 19, 1989/10

no abstracts in English

Journal Articles

Hot leg flow characteristics during two-phase natural circulation in pressurized water reactor

Kukita, Yutaka; Nakamura, Hideo; Anoda, Yoshinari; Tasaka, Kanji

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.465 - 470, 1989/10

no abstracts in English

Journal Articles

Results of 0.5 % cold leg break LOCA experiments at ROSA-IV/LSTF; Effect of break orientation

; Tasaka, Kanji; *; Kukita, Yutaka; Yonomoto, Taisuke

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.206 - 213, 1989/10

no abstracts in English

JAEA Reports

Recirculation pump suction line 75 and 25% split break LOCA tests of ROSA-III; Runs 929 and 930 with HPCS failure

Nakamura, Hideo; Tasaka, Kanji; Suzuki, Mitsuhiro; Anoda, Yoshinari; Kumamaru, Hiroshige; Yonomoto, Taisuke; Murata, Hideo

JAERI-M 89-131, 260 Pages, 1989/09

JAERI-M-89-131.pdf:6.11MB

no abstracts in English

JAEA Reports

Loss of off-site power test of ROSA-III; Run 971 with HPCS failure

Nakamura, Hideo; Tasaka, Kanji; Suzuki, Mitsuhiro; Anoda, Yoshinari; Kumamaru, Hiroshige; Yonomoto, Taisuke; Murata, Hideo

JAERI-M 89-130, 127 Pages, 1989/09

JAERI-M-89-130.pdf:3.19MB

no abstracts in English

JAEA Reports

Experiment data of ROSA-III integral test Run 913; 15% split break without HPCS actuation

Yonomoto, Taisuke; Tasaka, Kanji; Anoda, Yoshinari; Kumamaru, Hiroshige; Nakamura, Hideo; Murata, Hideo; Suzuki, Mitsuhiro

JAERI-M 89-125, 210 Pages, 1989/09

JAERI-M-89-125.pdf:4.22MB

no abstracts in English

Journal Articles

Critical heat flux for uniformly heated rod bundle under high-pressure, low-flow and mixed inlet conditions

Kumamaru, Hiroshige; Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 26(5), p.544 - 557, 1989/05

no abstracts in English

JAEA Reports

BWR LOCA simulation test(Run 992) in ROSA-III program for a 10% main steam line break with ECCS double failures

Suzuki, Mitsuhiro; Anoda, Yoshinari; Kumamaru, Hiroshige; Nakamura, Hideo; Yonomoto, Taisuke; Koizumi, Yasuo; Murata, Hideo; Tasaka, Kanji

JAERI-M 89-034, 154 Pages, 1989/03

JAERI-M-89-034.pdf:3.86MB

no abstracts in English

190 (Records 1-20 displayed on this page)