Taisuke Yonomoto

发表

Similarity study of ROSA-III and fist large break cuonterpart tests to BWR large break LOCA

Hiroshige Kumamaru, Mitsuhiro Suzuki, Taisuke Yonomoto, 1987 .

Thermal–hydraulic characteristics of a next-generation reactor relying on steam generator secondary side cooling for primary depressurization and long-term passive core cooling

Taisuke Yonomoto, Iwao Ohtsu, Yoshinari Anoda, 1998 .

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

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

Research on safety systems for future reactors using the ROSA/LSTF facility

Taisuke Yonomoto, Masaya Kondo, Sergey Svetlov, 2002 .

Simulation of Multiple Steam Generator Tube Rupture(SGTR) Event Scenario

Taisuke Yonomoto, Young Seok Bang, Kwang Won Seul, 2003 .

RANS analyses on erosion behavior of density stratification consisted of helium–air mixture gas by a low momentum vertical buoyant jet in the PANDA test facility, the third international benchmark exercise (IBE-3)

Taisuke Yonomoto, Satoshi Abe, Masahiro Ishigaki, 2015 .

Study of safety features and accident scenarios in a fusion DEMO reactor

Taisuke Yonomoto, Haruhiko Takase, Takumi Hayashi, 2014 .

Experimental and numerical study on density stratification erosion phenomena with a vertical buoyant jet in a small vessel

Taisuke Yonomoto, Satoshi Abe, Masahiro Ishigaki, 2016 .

Graded approach for safety of research reactors

Taisuke Yonomoto, 2019 .

Core and System Design of Reduced-Moderation Water Reactor with Passive Safety Features

Taisuke Yonomoto, Takamichi Iwamura, Tsutomu Okubo, 2002 .

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

Hiroshige Kumamaru, Taisuke Yonomoto, Kanji Tasaka, 1990 .

PWR Small Break Loss-of-Coolant-Accident Experiment at ROSA-V/LSTF with a Combination of Secondary-Side Depressurization and Gravity-Driven Safety Injection

Taisuke Yonomoto, Masaya Kondo, Yutaka Kukita, 1997 .

Core Makeup Tank Behavior Observed During the Rosa-AP600 Experiments

Taisuke Yonomoto, Masaya Kondo, Richard R. Schultz, 1997 .

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 .

Influence of mesh non-orthogonality on numerical simulation of buoyant jet flows

Taisuke Yonomoto, Satoshi Abe, Masahiro Ishigaki, 2017 .

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 .

Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs

Taisuke Yonomoto, Hideo Nakamura, Yu Maruyama, 2011 .

ROSA/AP600 Testing: Facility Modifications and Initial Test Results

Hiroshige Kumamaru, Taisuke Yonomoto, Richard R. Schultz, 1996 .

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.:Using JAERI Modified Version of RELAP5/MOD2 Code

Taisuke Yonomoto, Yutaka Kukita, Hideaki Asaka, 1994 .

Analysis of System Thermal Hydraulic Responses for Passive Safety Injection Experiment at ROSA-IV/Large Scale Test Facility

Taisuke Yonomoto, Yutaka Kukita, Hideaki Asaka, 1994 .

Key Aspects of the Safety Study of a Water-Cooled Fusion DEMO Reactor ∗)

Taisuke Yonomoto, Takumi Hayashi, Hiroyasu Utoh, 2014 .

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

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

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 .