Shoji Kotake

发表

Basic Principles of Maintenance Management for R&D-Level Nuclear Power Plants

Shoji Kotake, 2016 .

Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Ryodai Nakai, Shoji Kotake, Kenji Kamiyama, 2011 .

Comparison of advanced fast reactor pool and loop configurations from the viewpoint of construction cost

Shoji Kotake, Yoshitaka Chikazawa, Shusaku Sawada, 2011 .

Current Status of Conceptual Design Study Toward the Demonstration Reactor of JSFR

Shoji Kotake, Yoshio Kamishima, Kazumi Aoto, 2010 .

Toward the Commercialization of FBR Cycle Systems Adapted to Various Social Needs: Current Status of the Feasibility Study on Commercialized FBR Cycle Systems

Ryodai Nakai, Shoji Kotake, Takashi Namba, 2004 .

Commercialized fast reactor cycle systems and reactor core performance of the promising fast reactors

Shoji Kotake, Yoshihiko Sakamoto, Yutaka Sagayama, 2005 .

Development of general methodology of safety analysis and evaluation for fusion energy systems (GEM-SAFE)☆

Shoji Kotake, Tetsuo Sawada, Ichiro Yanagisawa, 1990 .

Evaluation method for structural integrity assessment in core disruptive accident of fast reactor

Shoji Kotake, Shigenobu Kubo, Yoshio Kamishima, 2004 .

Fusion systems shoul￠be developed so that they are safe eno皿gh to be acceptable to the societa亘environ)ment and rational enough to tke technical feasibility. For the fusion systems,even the concepts are premature and the system character・

Shoji Kotake, Yoichi Fuji, 1985 .

Considerations on fusion systems safety.

Shoji Kotake, M. Nishikawa, Yoichi Fujii-E, 1985 .

Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results

Shoji Kotake, Kazumi Aoto, Mikio Toda, 2010 .

ICONE19-43600 STUDY ON IN-SERVICE INSPECTION AND REPAIR PROGRAM AND RELATED PLANT DESIGN FOR JAPAN SODIUM-COOLED FAST REACTOR (JSFR)

Shinichi Suzuki, Shoji Kotake, Shigenobu Kubo, 2011 .

Application of the general methodology of safety analysis and evaluation for fusion energy systems (GEMSAFE) to the FER design

Shoji Kotake, Takashi Yano, Tetsuo Sawada, 1993 .

Design features and cost reduction potential of JSFR

Shoji Kotake, Hiroki Hayafune, Atsushi Katoh, 2014 .

A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

Tomoyasu Mizuno, Shoji Kotake, Masakazu Ichimiya, 2007 .

ICONE19-44140 CONCEPTUAL DESIGN STUDY FOR THE DEMONSTRATION REACTOR OF JSFR : (1) CURRENT STATUS OF JSFR DEVELOPMENT

Shoji Kotake, Hiroki Hayafune, Kazumi Aoto, 2011 .

Safety of Generation IV reactors in light of engineering findings from the Fukushima Dai-ichi Nuclear Power Station accident

Ryodai Nakai, Akira Yamaguchi, Shoji Kotake, 2013 .

Evaluation Study on Construction Cost of FBR Cycle System

Shoji Kotake, Takashi Namba, Yasuhiro Enuma, 2005 .

Numerical method for analysis of turbulent liquid metal magnetohydrodynamic flow

Shoji Kotake, Hideo Araseki, S. Kotake, 1994 .

Selection of sodium coolant for fast reactors in the US, France and Japan

Christopher Grandy, Robert Hill, Shoji Kotake, 2013 .

Minor Actinide-Bearing Oxide Fuel Core Design Study for the JSFR

Tomoyasu Mizuno, Shoji Kotake, Takashi Ogawa, 2010 .

Development of Passive Shutdown System for SFR

Shoji Kotake, Takafumi Aoyama, Shigenobu Kubo, 2010 .

Safety Design Requirements for Safety Systems and Components of JSFR

Shoji Kotake, Hidemasa Yamano, Shigenobu Kubo, 2011 .

The result of a wall failure in-pile experiment under the EAGLE project

Shoji Kotake, Shigenobu Kubo, Ikken Sato, 2007 .

Elimination of recriticality potential for the Self-Consistent Nuclear Energy System

Shoji Kotake, Sa. Kondo, Hiroshi Endo, 2002 .

Evaluation of JSFR Key Technologies

Shoji Kotake, Yoshitaka Chikazawa, Hiroki Hayafune, 2012 .

Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor

Shoji Kotake, Kazumi Aoto, Takaya Ito, 2011 .

Demonstration of Control Rod Holding Stability of the Self Actuated Shutdown System in Joyo for Enhancement of Fast Reactor Inherent Safety

Shoji Kotake, Takafumi Aoyama, Takashi Sekine, 2007 .

Development of Advanced Loop-Type Fast Reactor in Japan

Shoji Kotake, Shigenobu Kubo, Yoshio Kamishima, 2010 .