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Journal Articles

The results of 5% small break LOCA tests and natural circulation tests at the ROSA-IV LSTF

Tasaka, Kanji; ; Koizumi, Yasuo; Osakabe, Masahiro;

Nucl.Eng.Des., 108(1-2), p.37 - 44, 1988/02

https://doi.org/10.1016/0029-5493(88)90054-4
 Times Cited Count：18 Percentile：82.44(Nuclear Science & Technology)

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：97.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle

Koizumi, Yasuo; ; ; Tasaka, Kanji

Nucl.Eng.Des., 99, p.157 - 165, 1987/00

https://doi.org/10.1016/0029-5493(87)90117-8
 Times Cited Count：12 Percentile：74.55(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core heat transfer analysis during a BWR LOCA simulation experiment at ROSA-III

; Koizumi, Yasuo; Tasaka, Kanji

Nucl.Eng.Des., 103, p.239 - 250, 1987/00

https://doi.org/10.1016/0029-5493(87)90277-9
 Times Cited Count：3 Percentile：37.73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

LOCA steam condensation loads in BWR mark II pressure suppression containment system

; ; ;

Nucl.Eng.Des., 102, p.225 - 228, 1987/00

https://doi.org/10.1016/0029-5493(87)90256-1
 Times Cited Count：5 Percentile：50.32(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural analysis of a Japanese BWR MARK-I containment under internal pressure loading

; Soda, Kunihisa;

Nucl.Eng.Des., 104, p.365 - 370, 1987/00

https://doi.org/10.1016/0029-5493(87)90215-9
 Times Cited Count：2 Percentile：29.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Natural circulation in parallel vertical channels with different heat inputs

; ; Seki, Masahiro

Nucl.Eng.Des., 104, p.133 - 143, 1987/00

https://doi.org/10.1016/0029-5493(87)90294-9
 Times Cited Count：14 Percentile：77.74(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characteristics of natural circulation flow in a bent loop with a U-shape-type cooler

; ; ; ; ; ; Hashimoto, Kazunori*

Nucl.Eng.Des., 99, p.413 - 421, 1987/00

https://doi.org/10.1016/0029-5493(87)90137-3
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR, Part II; HENDEL multi-channel test rig with twelve fuel rods

; ; ; ; ;

Nucl.Eng.Des., 102, p.11 - 20, 1987/00

https://doi.org/10.1016/0029-5493(87)90263-9
 Times Cited Count：7 Percentile：59.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Calculation of stress intensity factors of surface cracks in complex structures; Application of efficient computer program EPAS,J1

; ; Yagawa, Motoki*

Nucl.Eng.Des., 68, p.71 - 85, 1987/00

https://doi.org/10.1016/0029-5493(82)90041-3
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Comparison between fission gas release data and FEMAXI-IV code calculations

;

Nucl.Eng.Des., 101, p.267 - 279, 1987/00

https://doi.org/10.1016/0029-5493(87)90055-0
 Times Cited Count：25 Percentile：88.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR, Part I; HENDEL single-channel tests with uniform heat flux

; ; ; ; ;

Nucl.Eng.Des., 102, p.1 - 9, 1987/00

https://doi.org/10.1016/0029-5493(87)90262-7
 Times Cited Count：11 Percentile：72.10(Nuclear Science & Technology)

no abstracts in English

Journal Articles

BWR small break LOCA counterpart tests at ROSA-III and fist test facilities

Koizumi, Yasuo; ; Tasaka, Kanji; J.A.Findlay*; L.S.Lee*

Nucl.Eng.Des., 102, p.151 - 163, 1987/00

https://doi.org/10.1016/0029-5493(87)90247-0
 Times Cited Count：2 Percentile：29.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Investigation of pre- and post-dryout heat transfer of steam-water two-phase flow in a rod bundle

; Koizumi, Yasuo; Tasaka, Kanji

Nucl.Eng.Des., 102, p.71 - 84, 1987/00

https://doi.org/10.1016/0029-5493(87)90268-8
 Times Cited Count：19 Percentile：84.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Similarity study of ROSA-III and fist large bleak counterpart tests to BWR large bleak LOCA

; ; ; Tasaka, Kanji; J.A.Findlay*; W.A.Sutherland*

Nucl.Eng.Des., 103, p.223 - 238, 1987/00

https://doi.org/10.1016/0029-5493(87)90276-7
 Times Cited Count：1 Percentile：19.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A 10% cold leg break test at ROSA-IV large scale test facility

; ; R.R.Schultz*; Koizumi, Yasuo; ; Osakabe, Masahiro; ; Tasaka, Kanji

Nucl.Eng.Des., 102, p.165 - 170, 1987/00

https://doi.org/10.1016/0029-5493(87)90248-2
 Times Cited Count：7 Percentile：59.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Thermal cycling durability test of tungsten copper duplex structures for use as a divertor plate

Seki, Masahiro; Ogawa, Masuro; Minato, Akio; ; Tone, Tatsuzo;

Nucl.Eng.Des./Fusion, 5, p.205 - 213, 1987/00

no abstracts in English

Journal Articles

Lifetime analysis for fusion reactor first walls and divertor plates

; ; Minato, Akio; Tone, Tatsuzo

Nucl.Eng.Des./Fusion, 5, p.221 - 231, 1987/00

no abstracts in English

Journal Articles

Ductile fracture behavior of circumferentially cracked type 304 stainless steel piping under bending load

; ; ;

Nucl.Eng.Des., 94, p.221 - 231, 1986/00

https://doi.org/10.1016/0029-5493(86)90004-X
 Times Cited Count：6 Percentile：58.64(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of jet discharging test results under BWR and PWR loss of coolant accident conditions

;

Nucl.Eng.Des., 96, p.1 - 9, 1986/00

https://doi.org/10.1016/0029-5493(86)90157-3
 Times Cited Count：8 Percentile：66.37(Nuclear Science & Technology)

no abstracts in English

84 (Records 1-20 displayed on this page)