Published April 1992 | Version v1
Journal article

Standardization of procedures for the high-temperature crack growth testing for FBR materials in Japan

  • 1. Dept. of Mechanical Engineering, Univ. Tokyo (Japan)
  • 2. Research Inst., Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)
  • 3. Nuclear Power Div., Kawasaki Heavy Industries Co. Ltd., Tokyo (Japan)
  • 4. Japan Atomic Energy Research Inst., Ibaraki (Japan)
  • 5. Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corp., Ibaraki (Japan)

Description

To develop a standard procedure for testing high temperature crack growth behavior of LMFBR materials, a cooperative study was performed using type 304 stainless steel and FEM simulation. J- and J'-integrals (the same as C*) were selected as parameters to characterize crack growth behavior. Based on the evaluation of the experimental data and FEM analysis, a standard testing procedure was recommended. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
133
Journal Issue
3
Series
Nucl. Eng. Des.
Journal Page Range
465-473
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
SMiRT-10 post-conference seminar no. 5 on inelastic analysis, fracture and life prediction.
Dates
Aug 1989.
Place
Santa Barbara, CA (United States).