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JAEA Reports

Study on thermo-hydraulic behavior during reflood phase of a PWR-LOCA

Sugimoto, Jun

JAERI-M 88-262, 129 Pages, 1989/01

JAERI-M-88-262.pdf:3.48MB

no abstracts in English

JAEA Reports

Effect of core inlet water flow rate on reflooding phenomena in the forced feed SCTF core-I tests

Onuki, Akira; Iwamura, Takamichi; Adachi, Hiromichi

JAERI-M 88-166, 98 Pages, 1988/09

JAERI-M-88-166.pdf:2.1MB

no abstracts in English

Journal Articles

Scale effects on countercurrent gas-liquid flow in horizontal tube connected to an inclined riser

; ; Murao, Yoshio

Nucl.Eng.Des., 107, p.283 - 294, 1988/00

https://doi.org/10.1016/0029-5493(88)90036-2
 Times Cited Count：65 Percentile：97.57(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Assessment of TRAC-PF1/MOD1 for Countercurrent-annular and Stratified Flows

JAERI-M 85-219, 19 Pages, 1986/01

JAERI-M-85-219.pdf:0.63MB

no abstracts in English

Journal Articles

Analytical study of thermal response similarity between simulated fuel rods and nuclear fuel rods during reflood phase of PWR-LOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 23(4), p.315 - 325, 1986/00

https://doi.org/10.3327/jnst.23.315
 Times Cited Count：3 Percentile：40.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of counter-current two-phase flow in horizontal tube connected to inclined riser

Journal of Nuclear Science and Technology, 23(3), p.219 - 232, 1986/00

https://doi.org/10.3327/jnst.23.219

no abstracts in English

JAEA Reports

Report on Reflood Experiment of Grid Spacer Effect

; Murao, Yoshio

JAERI-M 84-131, 223 Pages, 1984/06

JAERI-M-84-131.pdf:4.14MB

no abstracts in English

Journal Articles

Analysis of saturated film boiling heat transfer in reflood phase of PWR-LOCA; Turbulent boundary layer model

Osakabe, Masahiro; Sudo, Yukio

Journal of Nuclear Science and Technology, 21(2), p.115 - 125, 1984/00

https://doi.org/10.3327/jnst.21.115
 Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of grid spacers on reflood heat transfer in PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 21(2), p.103 - 114, 1984/00

https://doi.org/10.3327/jnst.21.103
 Times Cited Count：11 Percentile：72.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Investigation of Reflood Models by Coupling REFLA-1D and Multi-Loop System Model

; Murao, Yoshio

JAERI-M 83-147, 49 Pages, 1983/09

JAERI-M-83-147.pdf:1.13MB

no abstracts in English

JAEA Reports

Evaluation Report on CCTF Core-I Reflood Tests C1-18(Run 37)and C1-8(Run 17); Investigation of the Effect of Water Remaining in the Loop Seal Section on Reflood Behavior

; Murao, Yoshio

JAERI-M 83-115, 98 Pages, 1983/07

JAERI-M-83-115.pdf:1.77MB

no abstracts in English

JAEA Reports

Effect of Upper Plenum Water Accumulation on Reflooding Phenomena Under Forced-Feed Flooding in SCTF Core-I Tests

Sudo, Yukio; ; ; Osakabe, Masahiro; ; Abe, Yutaka;

JAERI-M 83-114, 117 Pages, 1983/07

JAERI-M-83-114.pdf:2.77MB

no abstracts in English

JAEA Reports

Droplets Flow and Heat Transfer at Top Region of Core in Reflood Phase

Osakabe, Masahiro; ;

JAERI-M 83-022, 26 Pages, 1983/02

JAERI-M-83-022.pdf:0.86MB

no abstracts in English

Journal Articles

Experimental study of upper core quench in PWR reflood phase

Abe, Yutaka; Sudo, Yukio; Osakabe, Masahiro

Journal of Nuclear Science and Technology, 20(7), p.571 - 583, 1983/00

https://doi.org/10.3327/jnst.20.571
 Times Cited Count：6 Percentile：60.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in PWR-LOCAs

Iwamura, Takamichi; Osakabe, Masahiro; Sudo, Yukio

Journal of Nuclear Science and Technology, 20(9), p.743 - 751, 1983/00

https://doi.org/10.3327/jnst.20.743
 Times Cited Count：6 Percentile：60.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of partial flow blockage on core heat transfer in forced-feed reflood tests

Sudo, Yukio; Osakabe, Masahiro

Journal of Nuclear Science and Technology, 20(4), p.322 - 332, 1983/00

https://doi.org/10.3327/jnst.20.322
 Times Cited Count：13 Percentile：78.50(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Upper plenum dump during reflood in PWR loss-of-coolant accident

Sudo, Yukio; P.Griffith*

Journal of Nuclear Science and Technology, 18(7), p.487 - 500, 1981/00

https://doi.org/10.3327/jnst.18.487
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Comparison of simultaneous and sequential methods in the degradation of insulating materials for wires and cables under simulated LOCA

; Yoshida, Kenzo; ; ; ; Machi, Sueo

EIM-80-98, p.57 - 64, 1980/00

no abstracts in English

Journal Articles

Film boiling heat transfer during reflood phase in postulated PWR loss-of-coolant accident

Sudo, Yukio

Journal of Nuclear Science and Technology, 17(7), p.516 - 530, 1980/00

https://doi.org/10.3327/jnst.17.516
 Times Cited Count：35 Percentile：92.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of average void fraction in a vertical two-phase flow channel under low liquid velocity

Sudo, Yukio

Journal of Nuclear Science and Technology, 17(1), p.1 - 15, 1980/00

https://doi.org/10.3327/jnst.17.1
 Times Cited Count：15 Percentile：80.02(Nuclear Science & Technology)

no abstracts in English

22 (Records 1-20 displayed on this page)