U.S. Plant Experience With Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials by B. Grimmel, U. S. Nuclear Regulatory Commission

U.S. Plant Experience With Alloy 600 Cracking and Boric Acid Corrosion of Light-Water Reactor Pressure Vessel Materials

B. Grimmel, U. S. Nuclear Regulatory Commission

80 pages • missing pub info (editions)

nonfiction art technology informative medium-paced
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Description

This report includes a summary of foreign and domestic Alloy 600 cracking experience, an analysis of the Alloy 600 cracking susceptibility model for vessel head penetration (VHP) nozzles, and information on corrosion of pressure boundary materials...

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