Kanji Tasaka

发表

Hiroshige Kumamaru, Mitsuhiro Suzuki, Taisuke Yonomoto, 1987 .

Relevant thermalhydraulic aspects of new generation LWRs

Kanji Tasaka, F. D'Auria, Francesco Oriolo, 1993 .

Thermal-hydraulic behavior in a PIUS-type small-scale experiment

Kanji Tasaka, Hideo Murata, Masahiro Osakabe, 1989 .

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

Kanji Tasaka, J. A. Findlay, W. A. Sutherland, 1987 .

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

Taisuke Yonomoto, Kanji Tasaka, Richard R. Schultz, 1987 .

DCHAIN: code for analysis of build-up and decay of nuclides

Kanji Tasaka, K. Tasaka, 1977 .

Accomplishment of LOCA/ECCS experimental research at Japan Atomic Energy Research Institute.

Kanji Tasaka, Yoshio Murao, Yasuo Koizumi, 1984 .

Feedback control of a primary pump for safe and stable operation of a PIUS-type reactor

Kanji Tasaka, Yutaka Kukita, Imai Satoshi, 1993 .

Loop seal clearing and refilling during a PWR small-break LOCA

Kanji Tasaka, Hideo Nakamura, Yutaka Kukita, 1990 .

Mitsuhiro Suzuki, Kanji Tasaka, J. A. Findlay, 1986 .

Analysis of large break LOCA experiment at ROSA-III

Kanji Tasaka, Nobuaki Abe, 1985 .

Single and two-phase natural circulation in Westinghouse pressurized water reactor simulators: Phenomena, analysis and scaling

Kanji Tasaka, Richard R. Schultz, J. C. Chapman, 1987 .

The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF

Hiroshige Kumamaru, Taisuke Yonomoto, Kanji Tasaka, 1990 .

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

Hiroshige Kumamaru, Taisuke Yonomoto, Kanji Tasaka, 1987 .

Simulation Test of PWR Instrument Tube Break LOCA in ROSA-IV Program

Mitsuhiro Suzuki, Kanji Tasaka, 1987 .

Nonuniform steam generator U-tube flow distribution during natural circulation tests in ROSA-IV large scale test facility

Kanji Tasaka, Hideo Nakamura, Y. Kukita, 1988 .

Results of 0.5% cold-leg small-break LOCA experiments at ROSA-IV/LSTF: Effect of break orientation

Taisuke Yonomoto, Kanji Tasaka, Yutaka Kukita, 1990 .

Flow Regime Transition to Wavy Dispersed Flow for High-Pressure Steam/Water Two-Phase Flow in Horizontal Pipe.

Kanji Tasaka, Hideo Nakamura, Yutaka Kukita, 1995 .

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

Kanji Tasaka, Hideo Nakamura, Yutaka Kukita, 1988 .

Boiling Water Reactor Loss of Coolant Tests Single Failure Tests with ROSA-III

Kanji Tasaka, Nobuaki Abe, Kunihisa Soda, 1983 .

3.9 Boiling Water Reactor LOCA/ECCS Integral Tests at ROSA-III Facility of JAERI

Kanji Tasaka, Kunihisa Soda, Masayoshi Shiba, 1980 .

ROSA-III base test series for a large break loss-of-coolant accident in a boiling water reactor

Kanji Tasaka, Nobuaki Abe, Yoshinari Anoda, 1982 .

Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF.

Hiroshige Kumamaru, Kanji Tasaka, Masahiro Osakabe, 1988 .

Pressurized water reactor core instrument tube ruptures: experimental simulation at the ROSA-IV lstf

Kanji Tasaka, Hideo Nakamura, Yutaka Kukita, 1990 .

New theoretical model for two-phase flow discharged from stratified two-phase region through small break.

Taisuke Yonomoto, Kanji Tasaka, T. Yonomoto, 1988 .

Two-Phase Flow Pattern .and Heat Transfer during Core Uncovery

Kanji Tasaka, Masahiro Osakabe, Yasuo Koizumi, 1987 .

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

Taisuke Yonomoto, Kanji Tasaka, Yasuo Koizumi, 1987 .

ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor

Hiroshige Kumamaru, Mitsuhiro Suzuki, Taisuke Yonomoto, 1985 .

Simulation Experiment of Five Percent Small Break Loss-of-Coolant Accident of Boiling Water Reactor

Hiroshige Kumamaru, Kanji Tasaka, Yoshinari Anoda, 1983 .

Atmospheric-Pressure Small-Scale Thermal-Hydraulic Experiment of a PIUS-Type Reactor

Kanji Tasaka, Imai Satoshi, Yutaka Kukita, 1992 .