Investigation of Warm Prestress for the Case of Small ΔT During a Reactor Loss-of-Coolant Accident

[+] Author and Article Information
F. J. Loss, R. A. Gray, J. R. Hawthorne

Materials Science and Technology Division, Naval Research Laboratory, Washington, D. C. 20375

J. Pressure Vessel Technol 101(4), 298-304 (Nov 01, 1979) (7 pages) doi:10.1115/1.3454637 History: Received March 19, 1979; Online October 25, 2010


An experimental investigation was conducted to characterize the benefits of warm prestress (WPS) in limiting crack extension in the wall of a nuclear vessel during a LOCA-ECCS. The present research emphasized material behavior under conditions of a small ΔT between the temperature of WPS and the failure temperature as might occur during a LOCA. The results have demonstrated that fracture will not occur during a simultaneous unloading and cooling of the crack-tip region following WPS even though the critical KIc of the virgin material is achieved. Based on a statistical analysis, it is concluded that WPS produces an “effective” elevation in KIc ; furthermore, it is suggested that this elevation will limit crack extension in the vessel wall so as to retain the coolant.

Copyright © 1979 by ASME
Your Session has timed out. Please sign back in to continue.





Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In