Published 1984 | Version v1
Book

Stress corrosion cracking of expanded tube-to-tubesheet joints in steam generators

  • 1. Atomic Energy of Canada Ltd., Chalk River Nuclear Labs., Chalk River, Ontario

Description

The objective of this study was to evaluate the effect of hydraulic expansion and roller expansion on the SCC of Alloy-800 tubing used in CANDU-600 reactors. Although no SCC of Alloy-800 has been observed in nuclear steam generators, laboratory studies have shown that, like Alloy-600, this material is susceptible to SCC in concentrated sodium hydroxide solutions at 300lt. slashC(dkg). Such solutions may be produced by concentration of impurities under the sludge that forms on the secondary side of the tubesheet during operation. Therefore, it is important to evaluate the effect of expansion techniques on residual stresses and SCC of the tube material

Additional details

Publishing Information

Publisher
National Association of Corrosion Engineers.
Imprint Place
Houston, TX (USA)
Imprint Title
Environmental degradation of materials in nuclear power systems-water reactors
Journal Page Range
p. 810-823.

Conference

Title
Environmental degradation of materials in nuclear power systems-water reactors.
Dates
22-24 Aug 1983.
Place
Myrtle Beach, SC (USA).