Author

Osamu Kawabata

Observed institution: Japan Nuclear Energy Safety Organization

OpenAlex ID: A5030302575

Analyses of Ex-Vessel Steam Explosion and Its Structural Dynamic Response for a Typical PWR Plant

2004 · Osamu Kawabata · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2

Level-2 PSA for the Prototype Fast Breeder Reactor MONJU Applied to the Accident Management Review

2012 · Hiroshi Endô, Osamu Kawabata, et al. · 1

Analysis of Hydrogen Behavior in a PWR Containment Vessel under Spray Operations

2001 · Osamu Kawabata, Takuji Nagayoshi, et al. · NCSU Libraries Repository (North Carolina State University Libraries) · 1

Icone19-43796 Development of Azores Code Analyzing Severe Accident Sequences for a Typical Fbr Plant

2011 · Osamu Kawabata, Hiroshi Endo, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Development of Azores Code Analyzing Severe Accident Sequences for a Typical Fbr Plant

2011 · Osamu Kawabata, Endo Hiroshi, et al.

Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor (Annual safety research report, JFY 2010)

2011 · Hiroshi Endô, Masaaki Inoue, et al.

Natural Circulation and Creep Damage Analyses of Severe Accident for a Typical PWR Plant

2009 · Osamu Kawabata, Masao Ogino · The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Uncertainty analysis on containment failure frequency for a japanese PWR plant

2007 · Osamu Kawabata, M. Kajimoto

Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

2006 · Osamu Kawabata, Mitsuhiro Kajimoto · The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Analyses of ex-vessel steam explosion and its structural dynamic response for a typical PWR plant

2004 · Osamu Kawabata

Hydrogen Detonation Analysis for a PWR Containment Vessel

2001 · Mitsuhiro Kajimoto, Takuji Nagayoshi, et al. · NCSU Libraries Repository (North Carolina State University Libraries)

Evaluation on a Containment Failure Frequency Considered Mitigation Accident Managements for a Japanese PWR Plant

2001 · Osamu Kawabata, Nobuo Tanaka, et al. · NCSU Libraries Repository (North Carolina State University Libraries)

Evaluation of containment failure frequency for a Japanese 4 loop PWR plant with a large dry pre-stressed concrete containment

2000 · Osamu Kawabata, Mitsuhiro Kajimoto, et al.

Effects of severe accident management measures on radionuclide behavior for BWR-5 with Mark-2 containment

2000 · Mitsuhiro Kajimoto, Kyoko Funayama, et al.

Analysis of radionuclide behavior during containment venting for BWR-5 plant with Mark-2 containment

2000 · Mitsuhiro Kajimoto, Osamu Kawabata, et al.

Demonstration test of analytical code for fluid-structure interaction phenomena under PWR loss of coolant accident

1983 · Shigehiko Mori, Osamu Kawabata, et al.

Works count: 16

Citation count: 4

H-index: 1

I10-index: