Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation

Jun Min Seo, Hune Tae Kim, Yun Jae Kim, Hiroyuki Yamada, Tomohisa Kumagai, Hayato Tokunaga, Naoki Miura

Research output: Contribution to journalArticlepeer-review

12 Citations (Scopus)

Abstract

In this paper, smooth and notched bar tensile tests of austenitic stainless steel 304 are performed, covering four different multi-axial stress states and six different strain rate conditions, to investigate the effect of the stress triaxiality and strain rate on fracture strain. Test data show that the measured true fracture strain tends to decrease with increasing stress triaxiality and strain rate. The test data are then quantified using the Johnson-Cook (J-C) fracture strain model incorporating combined effects of the stress triaxiality and strain rate. The determined J-C model can predict true fracture strain overall conservatively with the difference less than 20%. The conservatism in the strain-based acceptance criteria in ASME B&PV Code, Section III, Appendix FF is also discussed.

Original languageEnglish
Pages (from-to)2386-2394
Number of pages9
JournalNuclear Engineering and Technology
Volume54
Issue number7
DOIs
Publication statusPublished - 2022 Jul

Bibliographical note

Funding Information:
Part of this work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT) (No.NRF-2019M2D2A2048296). We acknowledge to Mr. Tsunemoto Yoshik, CRIEPI to obtain supporting experimental results.

Funding Information:
Part of this work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT) (No. NRF-2019M2D2A2048296 ). We acknowledge to Mr. Tsunemoto Yoshik, CRIEPI to obtain supporting experimental results.

Publisher Copyright:
© 2022 Korean Nuclear Society

Keywords

  • Austenitic stainless steel
  • Fracture strain
  • Strain rate
  • Strain-based acceptance criteria
  • Stress triaxiality

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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