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Journal Articles

Characteristics of countercurrent gas-liquid two-phase flow in vertical tubes

*;

Journal of Nuclear Science and Technology, 19(12), p.985 - 996, 1982/00

https://doi.org/10.3327/jnst.19.985
 Times Cited Count：43 Percentile：95.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characteristics of cocurrent two-phase downflow in tubes; Flow pattern,void fraction and pressure drop

; *

Journal of Nuclear Science and Technology, 16(4), p.245 - 255, 1979/00

https://doi.org/10.3327/jnst.16.245
 Times Cited Count：46

no abstracts in English

Journal Articles

Fuel rod vibration induced by coolant flow in rod assembly

;

Nihon Genshiryoku Gakkai-Shi, 20(1), p.61 - 70, 1978/01

https://doi.org/10.3327/jaesj.20.61
 Times Cited Count：0

no abstracts in English

Journal Articles

Hydrodynamic and hydraulic studies on void fractions in two-phase flow

; *

Journal of Nuclear Science and Technology, 15(12), p.886 - 898, 1978/00

https://doi.org/10.3327/jnst.15.886
 Times Cited Count：3

no abstracts in English

Journal Articles

Void fraction correlation for boiling and non-boiling vertical two-phase flows in tube

; *

Journal of Nuclear Science and Technology, 13(12), p.701 - 707, 1976/12

https://doi.org/10.3327/jnst.13.701
 Times Cited Count：11

no abstracts in English

JAEA Reports

Burnout Heat Flux of Narrow-Spaced Rod Bundle-Effect of Flow Rate and Steam Quality

; ;

JAERI-M 6031, 33 Pages, 1975/03

JAERI-M-6031.pdf:0.95MB

no abstracts in English

JAEA Reports

Effect of Heated Length on the Burnout Heat Flux of Rod Bundle Test Section

; ; ;

JAERI-M 6030, 26 Pages, 1975/03

JAERI-M-6030.pdf:0.8MB

no abstracts in English

JAEA Reports

Vibration of ATR Fuel Rods

;

JAERI-M 5885, 42 Pages, 1974/11

JAERI-M-5885.pdf:1.22MB

no abstracts in English

Journal Articles

Introduction to Reactor Safety(11)

;

Genshiryoku Kogyo, 20(7), p.71 - 74, 1974/07

http://ci.nii.ac.jp/naid/40017723367

no abstracts in English

JAEA Reports

Corrosion of Austenitic Stainless Steels in Liquid Lithium,I; Results of 1100-hour Test at 400,500 and 600$$^{circ}$$C in Natural Lithium Circulation Corrosion Testing Apparatus

; ; ;

JAERI-M 5683, 32 Pages, 1974/05

JAERI-M-5683.pdf:2.99MB

no abstracts in English

JAEA Reports

Vibration of JPDR-II Fuel Rod Induced by Coolant Flow

;

JAERI-M 5478, 87 Pages, 1973/12

JAERI-M-5478.pdf:3.94MB

no abstracts in English

JAEA Reports

Operation Report on the Low Temperature Fissiochmical Loop (LTFL),IV; Operations During the Period of April 1972 to March 1973

; ; ; Ikezoe, Yasumasa; Shimizu, Saburo; ;

JAERI-M 5421, 49 Pages, 1973/10

JAERI-M-5421.pdf:1.83MB

no abstracts in English

JAEA Reports

Operation Report on the Low Temperature Fissiochemical Loop (LTFL),III; Operations During the Period of April 1971 to March 1972

; ; Ikezoe, Yasumasa; Shimizu, Saburo; ; ; ; ; ;

JAERI-M 5360, 16 Pages, 1973/08

JAERI-M-5360.pdf:0.88MB

no abstracts in English

Journal Articles

Design and operational features of the low temperature fissiochemical loop

; ; Ikezoe, Yasumasa; ; ; ; ; *

Journal of Nuclear Science and Technology, 10(6), p.379 - 384, 1973/06

https://doi.org/10.3327/jnst.10.379

no abstracts in English

JAEA Reports

Operation Report on the Low Temperature Fissiochemical Loop(LTFL),II; Operation During the Period of April 1970 to March 1971

; ; ; Ikezoe, Yasumasa; ; ; ; ; ; *; et al.

JAERI-M 4920, 30 Pages, 1972/08

JAERI-M-4920.pdf:1.14MB

no abstracts in English

JAEA Reports

Energy Losses of Fission Fragments and Fission Fragment Dose Rates in Chemical Reaction Systems

; ; Ikezoe, Yasumasa; Shimizu, Saburo; ; ;

JAERI-M 4717, 35 Pages, 1972/02

JAERI-M-4717.pdf:1.14MB

no abstracts in English

JAEA Reports

Operation Report of Low Temperature Fissiochemical Loop(LTFL),I; Test Operations for the Period April 1969 through March 1970

; ; ; ; *; ; ; ; Ikezoe, Yasumasa;

JAERI-M 4630, 17 Pages, 1971/11

JAERI-M-4630.pdf:0.61MB

no abstracts in English

JAEA Reports

Conceptual Design of the Reactant Flow Loop for Fissiochemical Studies

; ; ; ; ; ; Ikezoe, Yasumasa; ; *; *; et al.

JAERI-M 4446, 46 Pages, 1971/05

JAERI-M-4446.pdf:1.33MB

no abstracts in English

Journal Articles

A Comparative Study on the Pressure Drop of Air-Water and Steam-Water Flows

;

Cocurrent Gas-Liquid Flow, p.359 - 380, 1969/00

no abstracts in English

Journal Articles

Flow and Heat Transmission in Nuclear Reactor

Kagaku Kogaku, 33(6), p.512 - 518, 1969/00

https://ci.nii.ac.jp/naid/40017554675

no abstracts in English

37 (Records 1-20 displayed on this page)