Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 72

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

RELAP5/MOD3 analysis of a ROSA-IV/LSTF loss-of-RHR experiment with a 5% cold leg break

C.J.Choi*; Nakamura, Hideo

Annals of Nuclear Energy, 24(4), p.275 - 285, 1997/00

 Times Cited Count:7 Percentile:53.76(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of ROSA-IV/LSTF 10% main steam line break test RUN SB-SL-01 using RELAP5/MOD3

H.Lee*; H.Seong*; G.Park*; Kumamaru, Hiroshige; Kukita, Yutaka

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 3, p.41 - 50, 1996/00

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

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

Analytical study on effect of reactor depressurization measures during LOCA sequences followed by loss of HPI in PWRs

Watanabe, Norio; *; *; Kumamaru, Hiroshige; Hirano, Masashi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1303 - 1310, 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

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

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF gravity-driven safety injection experiment Run SB-CL-27

Yonomoto, Taisuke; *; *; Anoda, Yoshinari; Kukita, Yutaka; ; Ito, Hideo; Osaki, Hideki; ; Nishikizawa, Tomotoshi; et al.

JAERI-M 94-069, 145 Pages, 1994/03

JAERI-M-94-069.pdf:4.07MB

no abstracts in English

Journal Articles

Steam generator tube rupture simulations

Anoda, Yoshinari; Nakamura, Hideo; Watanabe, Tadashi; Hirano, Masashi; Kukita, Yutaka

Int. Conf. on New Trends in Nuclear System Thermohydraulics,Vol. 1, 0, p.539 - 545, 1994/00

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

Quasi-static core liquid level depression and long-term core uncovery during a PWR LOCA

Kukita, Yutaka; R.R.Schultz*; Nakamura, Hideo; Katayama, Jiro*

Nucl. Saf., 34(1), p.33 - 48, 1993/01

no abstracts in English

Journal Articles

Loss of Residual Heat Removal(RHR) event during PWR mid-loop operation; ROSA-IV/LSTF experiment without opening on primary loop pressure boundary

Nakamura, Hideo; Katayama, Jiro; Kukita, Yutaka

Power Plant Transients,1992; FED-Vol. 140, p.9 - 16, 1993/00

no abstracts in English

Journal Articles

Experimental and analytical simulations of the Mihama Unit-2 steam generator tube rupture(SGTR) incident

Anoda, Yoshinari; Nakamura, Hideo; Watanabe, Tadashi; Hirano, Masashi; Kukita, Yutaka

Proc. of the 1993 Simulation Multiconference on the Int. Simulators Conf. ; SIMULATORS X, p.242 - 247, 1993/00

no abstracts in English

Journal Articles

Journal Articles

Code analysis of multidimensional phenomena in a ROSA-IV/LSTF experiment simulating a loss of residual heat removal event during PWR mid-loop operation

T.Chataing*; Nakamura, Hideo; Kukita, Yutaka

Proc. of the 2nd ASME/JSME Nuclear Engineering, p.247 - 254, 1993/00

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

Steam generator multiple U-tube rupture experiments on ROSA-IV/LSTF

Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka

Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2; NURETH 6, p.992 - 1001, 1993/00

no abstracts in English

Journal Articles

PWR cold-leg small-break LOCA with total HPI failure; Effect of break area on core dryout and intentional depressurization for prevention of excess core dryout

Kumamaru, Hiroshige; Kukita, Yutaka

Journal of Nuclear Science and Technology, 29(12), p.1162 - 1172, 1992/12

no abstracts in English

Journal Articles

Application of new coolant inventory tracking method to PWR small break LOCA simulation experiments at ROSA-IV/LSTF

Suzuki, Mitsuhiro

Journal of Nuclear Science and Technology, 29(6), p.547 - 558, 1992/06

no abstracts in English

72 (Records 1-20 displayed on this page)