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Journal Articles

Review on present state of human model researches in nuclear engineering and the prospect for their industrial applications

Yoshida, Kazuo

Nihon Genshiryoku Gakkai-Shi, 41(1), p.10 - 11, 1999/00

no abstracts in English

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

 Times Cited Count:16 Percentile:81.78(Nuclear Science & Technology)

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

 Times Cited Count:3 Percentile:36.68(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Break flow modeling for a steam generator tube rupture(SGTR) incident in a pressurized water reactor(PWR)

*; Watanabe, Tadashi; Kukita, Yutaka

JAERI-M 93-236, 34 Pages, 1993/12

JAERI-M-93-236.pdf:0.95MB

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

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

JAEA Reports

Vectorization and improvement of nuclear codes; MEUDAS4, FORCE, STREAM V2.6, HEATING7-VP, SCDAP/RELAP5/MOD2.5, NBI3DGFN

*; *; *; *; *; Yokokawa, Mitsuo

JAERI-M 92-142, 117 Pages, 1992/09

JAERI-M-92-142.pdf:2.45MB

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

Temporary core liquid level depression during a cold-leg small-break loss-of-coolant accident; The effect of break size and power level

*; Kumamaru, Hiroshige; *; Kukita, Yutaka; *

Nuclear Technology, 96, p.290 - 301, 1991/12

 Times Cited Count:5 Percentile:54.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

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

; Kukita, Yutaka

1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.197 - 202, 1991/00

no abstracts in English

Journal Articles

Two-phase natural circulation with reduced secondary water levels in a large-scale PWR simulator

Yonomoto, Taisuke; Kukita, Yutaka

Numerical Modelling of Basic Heat Transfer Phenomena in Nuclear Systems, p.75 - 82, 1991/00

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

CCFL characteristics of PWR steam generator U-tubes

Yonomoto, Taisuke; Anoda, Yoshinari; Kukita, Yutaka; Y.Peng*

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.522 - 529, 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

 Times Cited Count:18 Percentile:77.86(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

17 (Records 1-17 displayed on this page)
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