Grain boundary engineering of austenitic steel PNC316 for use in nuclear reactors

M. Sekine, N. Sakaguchi, M. Endo, H. Kinoshita, S. Watanabe, H. Kokawa, S. Yamashita, Y. Yano, M. Kawai

Research output: Contribution to journalArticle

22 Citations (Scopus)

Abstract

Austenitic stainless steel PNC316 was subjected to grain boundary engineering (GBE). It was found that the grain boundary engineered PNC316 (PNC316-GBEM) had a coincidence site lattice (CSL) fraction of 86% and that the network of random grain boundaries was perfectly divided by the CSL boundaries. The thermal stability and the void swelling behavior of PNC316-GBEM were investigated by means of SEM and TEM analyses. After thermal aging at 973 K for 100 h, structural changes were observed neither in the grain boundary networks of PNC316-GBEM nor in another sample of PNC316-GBEM subjected to 20% additional cold rolling, PNC316-GBEM20%CW. PNC316-GBEM showed a higher void swelling rate than as-received PNC316 (PNC316-AS). However, with additional 20% cold rolling after GBE, the void swelling rate decreased to as low as that of PNC316-AS.

Original languageEnglish
Pages (from-to)232-236
Number of pages5
JournalJournal of Nuclear Materials
Volume414
Issue number2
DOIs
Publication statusPublished - 2011 Jul 15

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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    Sekine, M., Sakaguchi, N., Endo, M., Kinoshita, H., Watanabe, S., Kokawa, H., Yamashita, S., Yano, Y., & Kawai, M. (2011). Grain boundary engineering of austenitic steel PNC316 for use in nuclear reactors. Journal of Nuclear Materials, 414(2), 232-236. https://doi.org/10.1016/j.jnucmat.2011.03.049