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Theoretical Analysis of Fracture Criterion for Stainless Steel Pipe with Circumferential Through-Wall Crack

  • K. Kashima
  • Y. Takahashi
Conference paper

Summary

The fracture criterion for nuclear reactor stainless steel piping was estimated using simplified methods. This estimation showed that the J-integral fracture criterion (the tearing modulus criterion) and the plastic collapse criterion were established almost simultaneously, and this confirmed the validity of conventional fracture criterion evaluation using the plastic collapse concept.

Keywords

Stress Intensity Factor Crack Length Fracture Criterion Plastic Collapse Stainless Steel Pipis 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

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    Harrison, R.P. CEGB Report No. R/H/R6-Rev. 2, 1980.Google Scholar
  2. 2.
    Ainsworth, R.A. et al.: Solutions to the Workshop Problem using the CEGB Fracture Assessment Procedure [R6], the CSNI/NRC Ductile Piping Fracture Mechanics Workshop, San Antonio, 1984.Google Scholar
  3. 3.
    Tada, H. et al.: The Stress Analysis of Cracks Handbook, Del Research Corporation, 1973.Google Scholar
  4. 4.
    NUPEC: Proving Test on SCC in BWR, 1984.Google Scholar
  5. 5.
    Ernst, H. et al.: ASTM STP 677, p. 581/599, 1979.Google Scholar

Copyright information

© Springer Japan 1986

Authors and Affiliations

  • K. Kashima
    • 1
  • Y. Takahashi
    • 1
  1. 1.Mechanical Engineering DepartmentCentral Research Institute of Electric Power Industry (CRIEPI)Komae, Tokyo, 201Japan

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