Hostname: page-component-78c5997874-xbtfd Total loading time: 0 Render date: 2024-11-20T00:18:24.014Z Has data issue: false hasContentIssue false
  • English
  • Français

Evaluation of the Susceptibility of Astm A216 Grade Wca Mild Steel to Stress Corrosion Cracking in Simulated Salt Repositopy Environments

Published online by Cambridge University Press:  28 February 2011

S. G. Pitman
S. G. Pitman*
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 099, Richland, Washington, 99352
Get access

Abstract

In current conceptual designs, a mild steel (ASTM A?16 Grade WCA) is the relerence container material for use in high level nuclear waste packages intended for emplacement in a salt repository. The resistance of the steel to stress corrosion crackinq (SCC) is being investigated as part of the effort underway to verify the suitability of the material for waste package applications. Static tests (U-bend and bolt-loaded fracture toughness specimens) and dynamic tests (slow strain rate and corrosion fatigue) were conducted on both as-cast and weldment specimens of the material, in both low-Mg and high-Mg halite-saturated brines, in the temperature range of 90 to 200°C. The investigations indicate that the steel is not susceptible to SCC under the test conditions employed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 84: Symposium L – Scientific Basis for Nuclear Waste Management X , 1986 , 239
Copyright
Copyright © Materials Research Society 1987

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Westerman, R. E. and Pitman, S. G.. Corrosion of Candidate IronBase Waste Package Structural Barrier Materials in Moist Salt Environments. International Symposiuma on the Scientific Fasis for Nuclear Waste Management VIII, November 1984, Boston, MA. Materials Research Society Symposia Proceedings, Vol. 44, pp. 279–285.Google Scholar
2. Westerman, R. E., Haberman, J. H., Pitman, S. G., Pulsipher, P. A., and Sigalla, L. A.. 1986. Corrosion and Environmental-Mechanical Characteristics of Iron-Base Nuclear Waste Package Structural Barrier Materials. PNL-5426, prepared for the Salt Repository Project of the U.S. Department of Energy, Pacific Northwest Laboratory, Richland, WA. Google Scholar
3. Westerman, R. E., Haberman, J. H., Pitman, S. G., and Perrin, J. S.. 1986. Corrosion of Iron-Base Waste Package Container Materials in Salt Environments. Proceedings of the 1986 Joint ASME/ANS Nuclear Power Conference, Philadelphia, PA. pp. 174–178.Google Scholar