Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
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Thermal Aging Embrittlement of High Chromium Oxide Dispersion Strengthened Steels

  • Lee, J.S. (Department of Nuclear and Quantum Engineering, KAIST) ;
  • Kim, I.S. (Department of Nuclear and Quantum Engineering, KAIST) ;
  • Jang, C.H. (Department of Nuclear and Quantum Engineering, KAIST) ;
  • Kimura, A. (Institute of Advanced Energy, Kyoto University) ;
  • Kim, B.G. (Korea Atomic Energy Research Institute) ;
  • Choo, K.N. (Korea Atomic Energy Research Institute) ;
  • Choo, Y.S. (Korea Atomic Energy Research Institute) ;
  • Kang, Y.H. (Korea Atomic Energy Research Institute)
  • Published : 2005.05.26
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Abstract

After thermal aging treatment at 693 K for 322 hours, any discernable precipitation could not be found in the $13{\sim}22$ Cr ODS steels, but showing an increase in SP-DBTT and reduction in upper shelf energy. The degree of aging embrittlement increases with Cr content such that the increases in SP-DBTT are 10, 50 and 73 K in 13, 16 and 19 Cr ODS steel, respectively. Amount of hardening also increased linearly as a function of Cr content. Based on the TEM observation, the origin of hardening must be related to the invisibly fine size of Cr-rich ${\acute{\alpha}}-phase$ (<1 nm).

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