Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors Page: 4 of 55
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TABLE OF CONTENTS (Contd.)
Page
3. Discussion . . . . . . . . . . . . . . . . . . . . . . 1
3.1. Mechanism of intergranular SACC. . . . . . . . . . . . . . . 19
3.1.1. Oxygen . . . . . . . . . . . . . . . . . . . . . . . 20
3.1.2. Caustic. . . . . . . . . . . . . . . . . . . . . . . 21
3.1.3. Hydrogen . . . . . . . . . . . . . . . . . . . . . . 22
4. Conclusions. . . . . . . . . . . . . . . . . . . . . . . . . . . . 23
REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25
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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.