Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors Page: 4 of 55

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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. (digital.library.unt.edu/ark:/67531/metadc1026645/m1/4/: accessed February 20, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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