Kenichi Takakura

A prediction model of IASCC initiation stress for bolts in PWR core internals

Hiromasa Nishioka, Katsuhiko Fujii, Koji Fukuya, 2010 .

Development of elevated temperature structural design guide for Japanese demonstration breeder reactor

Hiroshi Hirayama, Toshio Ueno, Hiroshi Ozaki, 1995 .

OS2506 Study on Structural Integrity Assessment for IASCC of BWR Plants : (2) Fracture Mechanics Investigation for IASCC Crack Growth in Core Shroud Structure

Takuya Ogawa, Masao Itatani, Toshiyuki Saito, 2011 .

IASCC Evaluation Method for Irradiated Core Internal Structures in BWR Power Plants

Yoshiyuki Kaji, Tomomi Nakamura, Kenichi Takakura, 2010 .

Creep-fatigue evaluation rules in design guide for DRBR in Japan

Hiroshi Wada, Hiroshi Hirayama, Hiroshi Ozaki, 1995 .

K-0804 Development of Structural Integrity Oriented Reliability Assessment System (SORE) For FBR MONJU (4) : Secondary Cooling System Piping

Hiroshi Hirayama, Hiroaki Tanabe, Kenichi Takakura, 2001 .