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Chapter 19
BWR Reactor Internals and Other BWR Issues

Excerpt

The objective of this Chapter is to provide some details of many and sometimes unique ways in which the provisions of Section III and Section XI have been used in addressing the service-induced degradations in the BWR vessels, internals, and pressure boundary piping. Among the items covered are reactor internals, weld overlays, and reactor vessel. The most common form of service-induced cracking in the stainless steel and Ni-Cr-Fe components in the BWR pressure boundary is typically due to intergranular stress corrosion cracking (IGSCC).

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