Published 2007 | Version v1
Miscellaneous

Stress corrosion cracking of steam generator tubing materials in lead containing solution

  • 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)

Description

Stress corrosion cracking (SCC) in lead (Pb) containing environments has been one of key issues in the nuclear power industry since Pb had been identified as a cause of the SCC of steam generator (SG) tubing materials in some power plants. To mitigate or prevent degradation of SG tubing materials, a mechanistic understanding of SCC in Pb containing environment is needed, along with an understanding of the source and transport behaviors of Pb species in the secondary circuit. In this work, SCC behaviors of Alloy 600 in Pb containing environments were studied. Influences of microstructures of Alloy 600 and the inhibitive additives were investigated using the C-ring and the slow strain rate tests in caustic solution and demineralized water at 315oC. Microstructures of Alloy 600 were varied by heat treatment at different temperatures. The additives examined were nickel boride (NiB) and cerium boride (CeB6). The surface films were analyzed using Auger Electron Spectroscopy (AES) and Energy Dispersive X-ray Spectroscopy (EDS). The SCC mode varied with microstructure. Effectiveness of the additives in Pb containing environments is discussed. (author)

Part of:
13th International conference on environmental degradation of materials in nuclear power systems

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-89-5
Imprint Title
13th International conference on environmental degradation of materials in nuclear power systems
Imprint Pagination
388 Megabytes
Journal Page Range
[13 p.]

Conference

Title
13. International conference on environmental degradation of materials in nuclear power systems
Dates
19-23 Aug 2007
Place
Whistler, BC (Canada)

Optional Information

Notes
11 refs., 3 tabs., 11 figs.