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Journal Articles

Intentional depressurization of steam generator secondary side during a PWR small-break loss-of-coolant accident

; Kukita, Yutaka

Journal of Nuclear Science and Technology, 32(2), p.101 - 110, 1995/02

https://doi.org/10.3327/jnst.32.101
 Times Cited Count：18 Percentile：83.3(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Subcritical to supercritical flow transition in a horizontal stratified flow

; Kukita, Yutaka; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.131 - 136, 1995/00

no abstracts in English

Journal Articles

Analysis of system thermal hydraulic responses for passive safety injection experiment at ROSA-IV/Large Scale Test Facility using JAERI modified version of RELAP5/MOD2 code

; Yonomoto, Taisuke; Kukita, Yutaka

Journal of Nuclear Science and Technology, 31(12), p.1265 - 1274, 1994/12

https://doi.org/10.3327/jnst.31.1265
 Times Cited Count：3 Percentile：35.79(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Analysis of ROSA-IV/LSTF experiment simulating a steam generator tube rupture design basis incident by using RELAP5/MOD2 code

Watanabe, Tadashi; M.Wang*; Kukita, Yutaka

JAERI-M 93-039, 26 Pages, 1993/03

JAERI-M-93-039.pdf:0.85MB

no abstracts in English

JAEA Reports

Analysis of ROSA-IV/LSTF experiment simulating the Mihama Unit-2 steam generator U-tube rupture incident by using RELAP5/MOD2 code

Watanabe, Tadashi; Kukita, Yutaka

JAERI-M 93-008, 23 Pages, 1993/02

JAERI-M-93-008.pdf:0.84MB

no abstracts in English

Journal Articles

Experiment and analyses of PWR station blackout transient involving pump seal leak

Watanabe, Tadashi; Kukita, Yutaka

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2, p.1232 - 1239, 1993/00

no abstracts in English

Journal Articles

Primary feed-and-bleed experiments at ROSA-IV LSTF

; Kukita, Yutaka

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2, p.1361 - 1367, 1993/00

no abstracts in English

Journal Articles

Analysis of experiment simulating Mihama Unit-2 steam generator U-tube rupture incident by using RELAP5/MOD2

Watanabe, Tadashi; Kukita, Yutaka

Best Estimate Safety Analysis, p.1 - 7, 1992/00

no abstracts in English

Journal Articles

User effects on RELAP5/MOD2 analysis of ROSA-IV/LSTF cold-leg break LOCA experiment

Watanabe, Tadashi; Kukita, Yutaka; *

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.349 - 357, 1991/00

no abstracts in English

Journal Articles

Loss of residual heat removal(RHR) during PWR MID-loop operation; Experiments in ROSA-IV/LSTF

Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.497 - 503, 1991/00

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

https://doi.org/10.1016/0894-1777(90)90075-I
 Times Cited Count：18 Percentile：76.57(Thermodynamics)

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

12 (Records 1-12 displayed on this page)
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