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Search Results: Records 1-20 displayed on this page of 72

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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

https://doi.org/10.1016/S0306-4549(96)00072-2
 Times Cited Count：7 Percentile：52.72(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

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

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

https://doi.org/10.3327/jnst.31.1265
 Times Cited Count：3 Percentile：35.79(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

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

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

Characteristic responses of core exit thermocouples during inadequate core cooling in small break LOCA experiments conducted at large-scale test facility(LSTF) of ROSA-IV program

Suzuki, Mitsuhiro

Proc. of the 2nd ASME/JSME Nuclear Engineering, p.63 - 68, 1993/00

no abstracts in English

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

https://doi.org/10.3327/jnst.29.1162

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

https://doi.org/10.3327/jnst.29.547

no abstracts in English

72 (Records 1-20 displayed on this page)