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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

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

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

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

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

JAEA Reports

BWR Main Steam Line Break LOCA Tests Runs 951,954 and 956 at ROSA-III; Break Area Effects with HPCS Failure-

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

JAERI-M 85-202, 295 Pages, 1985/12

JAERI-M-85-202.pdf:7.72MB

no abstracts in English

JAEA Reports

Comparisons of ROSA-III and FIST BWR Loss of Coolant Accident Simulation Tests

Tasaka, Kanji; ; Koizumi, Yasuo; ; ; ; ; J.A.Findlay*; W.A.Sutherland*; W.S.Hwang*; et al.

JAERI-M 85-158, 73 Pages, 1985/10

JAERI-M-85-158.pdf:1.81MB

no abstracts in English

JAEA Reports

ROSA-III 50% Break Integral Test RUN 916; Break Area Parameter Test

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

JAERI-M 85-109, 160 Pages, 1985/08

JAERI-M-85-109.pdf:4.18MB

no abstracts in English

JAEA Reports

BWR Recirculation Loop Discharge Line Break LOCA Tests with Break Areas 50% and 100% Assuming HPCS Failure at ROSA-III Test Facility

; Tasaka, Kanji; ; ; ; ; ; *;

JAERI-M 85-037, 224 Pages, 1985/03

JAERI-M-85-037.pdf:5.99MB

no abstracts in English

JAEA Reports

A Main Steam Line Break Experiment at ROSA-III, Run 953; 100% Break with an HPCS Failure

; ; ; Tasaka, Kanji; ; ; ; ;

JAERI-M 85-029, 188 Pages, 1985/03

JAERI-M-85-029.pdf:4.47MB

no abstracts in English

Journal Articles

Experiment analysis of power curve sensitivity test series at ROSA-III

Koizumi, Yasuo; *; ; Tasaka, Kanji

Nucl.Eng.Des., 86, p.267 - 287, 1985/00

https://doi.org/10.1016/0029-5493(85)90227-4
 Times Cited Count：4 Percentile：54.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ROSA-III double-ended break test series for a loss-of-coolant accident in a boiling water reactor

Tasaka, Kanji; ; ; Koizumi, Yasuo; ;

Nuclear Technology, 68, p.77 - 93, 1985/00

https://doi.org/10.13182/NT85-A33569
 Times Cited Count：8 Percentile：71.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Recirculation pump discharge line break test at ROSA-III for a boiling water reactor

; Tasaka, Kanji; ; ; ;

Nuclear Technology, 70, p.189 - 203, 1985/00

https://doi.org/10.13182/NT85-A33643
 Times Cited Count：2 Percentile：37.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analyses of ROSA-III break area spectrum experiments in a BWR loss-of-coolant accident

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

Nuclear Technology, 71, p.628 - 642, 1985/00

https://doi.org/10.13182/NT85-A33685
 Times Cited Count：5 Percentile：59.84(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Main steam line break experiment at ROSA-III-Run 952 (Standard run with full ECCS)

; ; ; Tasaka, Kanji; ; ; ; ;

JAERI-M 84-229, 153 Pages, 1984/12

JAERI-M-84-229.pdf:4.01MB

no abstracts in English

JAEA Reports

Recirculation Pump Suction Line 200% Break Integral Test at ROSA-III with Two LPCI Failures,RUN 983

; ; Tasaka, Kanji; ; ; ; ;

JAERI-M 84-135, 206 Pages, 1984/08

JAERI-M-84-135.pdf:4.94MB

no abstracts in English

JAEA Reports

Recirculation Pump Suction Line 2.8% Break Integral Test at ROSA-III with HPCS Failure, Run 984

; ; Tasaka, Kanji; ; ; ; ;

JAERI-M 84-100, 197 Pages, 1984/06

JAERI-M-84-100.pdf:4.49MB

no abstracts in English

39 (Records 1-20 displayed on this page)