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Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-Alloy RPV Steels

  • Z. QueEmail author
  • H. P. Seifert
  • P. Spätig
  • G. S. Rao
  • S. Ritter
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

The structural integrity of the reactor pressure vessel (RPV) of light water reactors (LWR) is of utmost importance regarding operation safety and lifetime. The fracture behaviour of low-alloy RPV steels with different DSA (dynamic strain aging) & EAC (environmental assisted cracking) susceptibilities and microstructures (base metal, simulated weld coarse grain heat affected zone) in simulated LWR environments was evaluated by elastic plastic fracture mechanics (EPFM) tests with different strain rates and by metallo- and fractographic post-test observations. These tests revealed some evidences of high-temperature water and hydrogen effects on the fracture behaviour and potential synergies with DSA and EAC.

Keywords

Low alloy steel Hydrogen embrittlement Dynamic strain aging Environmental assisted cracking Fracture resistance reduction 

Notes

Acknowledgements

Funding for the SAFE-II project from the Swiss Federal Nuclear Safety Inspectorate (ENSI) is gratefully acknowledged. The authors would like to express their gratitude for the experimental contributions and helpful suggestions from H. Kottmann, D. Stammbach, B. Baumgartner, R. Schwenold, J. Bai and E. Mueller from Paul Scherrer Institute.

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Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Z. Que
    • 1
    Email author
  • H. P. Seifert
    • 1
  • P. Spätig
    • 1
  • G. S. Rao
    • 1
  • S. Ritter
    • 1
  1. 1.Laboratory for Nuclear MaterialsPaul Scherrer InstitutVilligen PSISwitzerland

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