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JAEA Reports

ROSA-III tests on BWR pump suction-line 200% break LOCAs with partial and total ECCS failure; RUN 924(LPCS and one LPCI pump failure), RUN 902(Two LPCI pump failure) and RUN 905(Total ECCS failure)

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

JAERI-M 91-167, 293 Pages, 1991/10

JAERI-M-91-167.pdf:7.69MB

no abstracts in English

JAEA Reports

A BWR pump suction-line 200% break test at ROSA-III program(RUN 903); Effect of prolonged recirculation pump operation

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

JAERI-M 91-103, 156 Pages, 1991/07

JAERI-M-91-103.pdf:4.59MB

no abstracts in English

JAEA Reports

An Intermediate break BWR LOCA test(Run991) at ROSA-III; Simulation of ECCS line break LOCA phenomena

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

JAERI-M 90-073, 160 Pages, 1990/04

JAERI-M-90-073.pdf:3.9MB

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

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

Intentional coolant system depressurization; Experimental studies in the ROSA-III and ROSA-IV programs

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

CSNI-R-158, p.449 - 466, 1989/00

no abstracts in English

Journal Articles

BWR natural circulation experiments at ROSA-III under low-power and reduced inventory conditions

; ; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 25(2), p.143 - 152, 1988/02

https://doi.org/10.3327/jnst.25.143

no abstracts in English

Journal Articles

BWR loss-of-coolant accident tests at ROSA-III with high temperature emergency core coolant injection

; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 25(2), p.169 - 179, 1988/02

https://doi.org/10.3327/jnst.25.169

no abstracts in English

Journal Articles

Investigation of effect of pressure control system on BWR-LOCA phenomena using ROSA-III test facility

; Koizumi, Yasuo; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 24(10), p.844 - 858, 1987/10

https://doi.org/10.3327/jnst.24.844
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

BWR 2% Main Recirculation Line Break LOCA Tests Runs 915 and 920 without HPCS in ROSA-III Program; Effects of Pressure Control System

; ; ; ; ; Koizumi, Yasuo; Tasaka, Kanji

JAERI-M 87-043, 220 Pages, 1987/03

JAERI-M-87-043.pdf:5.2MB

no abstracts in English

Journal Articles

Effect of heat generation difference among fuel bundles on core thermal-hydraulics during 200% and 5% loss-of-coolant accident experiments at ROSA-III

Koizumi, Yasuo; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 24(1), p.61 - 74, 1987/01

https://doi.org/10.3327/jnst.24.61
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core heat transfer analysis during a BWR LOCA simulation experiment at ROSA-III

; Koizumi, Yasuo; Tasaka, Kanji

Nucl.Eng.Des., 103, p.239 - 250, 1987/00

https://doi.org/10.1016/0029-5493(87)90277-9
 Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

BWR small break LOCA counterpart tests at ROSA-III and fist test facilities

Koizumi, Yasuo; ; Tasaka, Kanji; J.A.Findlay*; L.S.Lee*

Nucl.Eng.Des., 102, p.151 - 163, 1987/00

https://doi.org/10.1016/0029-5493(87)90247-0
 Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Similarity study of ROSA-III and fist large bleak counterpart tests to BWR large bleak LOCA

; ; ; Tasaka, Kanji; J.A.Findlay*; W.A.Sutherland*

Nucl.Eng.Des., 103, p.223 - 238, 1987/00

https://doi.org/10.1016/0029-5493(87)90276-7
 Times Cited Count：1 Percentile：19.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Investigation of break location effects on thermal-hydraulics during intermediate break loss-of-coolant accident experiments at ROSA-III

Koizumi, Yasuo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 23(11), p.1008 - 1017, 1986/11

https://doi.org/10.3327/jnst.23.1008
 Times Cited Count：3 Percentile：40.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

BWR 200% recirculation pump suction line break LOCA tests,Runs 942 and 943 at ROSA-III without HPCS; Effects of initial fluid conditions on LOCA

; Tasaka, Kanji; ; ; ; ; ; Koizumi, Yasuo

JAERI-M 86-038, 275 Pages, 1986/03

JAERI-M-86-038.pdf:6.4MB

no abstracts in English

JAEA Reports

Recirculation Pump Suction Line 1% Split Break LOCA Test of ROSA-III; Runs 921 and 931 with HPCS Failure

; Tasaka, Kanji; Koizumi, Yasuo; ; ; ; ;

JAERI-M 85-209, 236 Pages, 1986/01

JAERI-M-85-209.pdf:6.11MB

no abstracts in English

Journal Articles

Similarity study of large steam line break LOCA in ROSA-III, FIST and BWR/6

; J.A.Findlay*; Tasaka, Kanji; W.A.Sutherland*

Nucl.Eng.Des., 98, p.39 - 55, 1986/00

https://doi.org/10.1016/0029-5493(86)90119-6
 Times Cited Count：1 Percentile：20.71(Nuclear Science & Technology)

no abstracts in English

75 (Records 1-20 displayed on this page)