Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors Page: 1 of 55
This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided to Digital Library by the UNT Libraries Government Documents Department.
The following text was automatically extracted from the image on this page using optical character recognition software:
( ' /
INTERGRANULAR STRESS-ASSISTED CORROSION CRACKING
OF AUSTENITIC ALLOYS IN WATER-COOLED NUCLEAR REACTORS
Craig F. Cheng
This report was prepared as an account of work
sponsored by the United States Government. Neither
the United States ,or the United States Atomic Energy
Cemmissicn, nor any of their employees, nor any of
their castrasters, subcontractors, or their emplo:'-.
I makes any warranty, express or implied, or assumes any
legal trabilsi r orespnsbhlity for the accuracy, com-
pleteness or usefulness of any information, apparatus,
product or pr.:e-ss disctsssd, ot represents that its use
,.sId not infrnge prnalely owned rights.
For Presentation At:
5th European Congress on Corrosion,
Paris, France, September 24-28, 1973
U et C SilA USAEC
ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS
Here’s what’s next.
This article can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Article.
Cheng, C.F. Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors, article, August 1, 1974; Illinois. (digital.library.unt.edu/ark:/67531/metadc1026645/m1/1/: accessed December 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.