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

Korean Nuclear Society (한국원자력학회)
권호 표지

Assessment of $13{\sim}19%Cr$ Ferritic Oxide Dispersion Strengthened Steels for Fuel Cladding Applications

  • Lee, J.S. (Center for Advanced Reactor Research, KAIST) ;
  • Kim, I.S. (Department of Nuclear and Quantum Engineering, KAIST) ;
  • Kimura, A. (Institute of Advanced Energy, Kyoto University) ;
  • Choo, K.N. (Korea Atomic Energy Research Institute) ;
  • Kim, B.G. (Korea Atomic Energy Research Institute) ;
  • Choo, Y.S. (Korea Atomic Energy Research Institute) ;
  • Kang, Y.H. (Korea Atomic Energy Research Institute)
  • Published : 2004.10.28
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Abstract

1. Cathodic hydrogen charging considerably reduced the tensile ductility of ODS steels and a 9Cr-2W RMS. The hydrogen embrittlement of ODS steels was strongly affected by specimen sampling orientation, showing significant embrittlement in the T-direction. This comes from the microstructural anisotropy caused by elongated grains of ODS steels in L-direction. 2. The ODS steels contained a higher concentration of hydrogen than 9Cr-2W RMS at the same cathodic charging condition, and the critical hydrogen concentration required to transition from ductile to brittle fracture was in the range of $10{\sim}12$ wppm, which approximately 10 times larger than that of a 9Cr-2W martensitic steel. 3. The ODS steels showed a typical ductile to brittle transition behavior and it strongly depended on the specimen sampling direction, namely L- and T-direction. In T-direction, the SP-DBTT was about 170 L, irrespective of the ODS materials, and L-direction showed a lower SP-DBTT than that of T-direction.

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