Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors Page: 1 of 55
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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
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Cheng, C.F. Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors, article, August 1, 1974; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1026645/m1/1/: accessed March 26, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.