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Interstitial-Impurity Radiation-Defect Interactions in Ferritic Steels

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Abstract

This paper summarizes the effects of interactions between interstitial impurity atoms and radiation produced defects on the mechanical and fracture characteristics of ferritic steels. It emphasizes radiation embrittlement and pressurized thermal shock phenomena associated with pressure boundary materials in light water reactors. Evidence is presented for the existence of strain-aging in pressure vessel steels. Also examined are earlier results on controlled neutron irradiation experiments on iron and mild steel, the author’s recent work on radiation effects in low carbon mild steel and the behavior of nuclear pressure vessel steel. Relevant results obtained at NC State (USA), Aktiebola-get Atomenergi (Sweden), AERE (UK) and BARC (India) are reviewed.

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Authors
  1. K. Linga Murty
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Additional information

K. Linga Murty received his Ph.D. in applied physics from Cornell University. He is currently Professor and the Graduate Administrator in the Department of Nuclear Engineering and is associated with the Department of Materials Engineering at North Carolina State University in Raleigh, North Carolina. Dr. Murty is also a member of TMS.

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Linga Murty, K. Interstitial-Impurity Radiation-Defect Interactions in Ferritic Steels. JOM 37, 34–39 (1985). https://doi.org/10.1007/BF03258766

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