Influences of the dynamic strain aging on the J–R fracture characteristics of the ferritic steels for reactor coolant piping system

K.C Kim, J.T Kim, J.I Suk, U.H Sung, H.K Kwon
  • Nuclear Engineering and Design, March 2004, Elsevier
  • DOI: 10.1016/j.nucengdes.2003.06.014

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The following have contributed to this page: Kuk-Cheol Kim