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Fundamentals of Radiation Materials Science pp 951–985Cite as

Effects of Irradiation on Corrosion and Environmentally Assisted Cracking

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Abstract

A growing concern for electric power utilities worldwide has been the degradation of core components in nuclear power reactors, which provide approximately 17 % of the world’s electric power needs. Service failures have occurred in boiling water reactor (BWR) core components and, to a somewhat lesser extent, in pressurized water reactor (PWR) core components consisting of iron- and nickel-base stainless alloys that have achieved a significant neutron fluence in environments that span oxygenated to hydrogenated water at 270–340 °C. Because cracking susceptibility depends on many factors, such as alloy composition and microstructure, stress, radiation, and the environment, the failure mechanism has been termed irradiation-assisted stress corrosion cracking (IASCC).

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Authors and Affiliations

  1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 1921 Cooley Bldg., 2355 Bonisteel Blvd., Ann Arbor, MI, 48109-2104, USA

    Gary S. Was

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Correspondence to Gary S. Was .

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Was, G.S. (2017). Effects of Irradiation on Corrosion and Environmentally Assisted Cracking. In: Fundamentals of Radiation Materials Science. Springer, New York, NY. https://doi.org/10.1007/978-1-4939-3438-6_16

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  • DOI: https://doi.org/10.1007/978-1-4939-3438-6_16

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  • Online ISBN: 978-1-4939-3438-6

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