SUSCEPTIBILITY OF ALLOY 690 TO STRESS CORROSION CRACKING IN CAUSTIC AQUEOUS SOLUTIONS

Author:

KIM DONG-JIN,KIM HONG PYO,HWANG SEONG SIK

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. J. Benson, 29th Annual EPRI Steam Generator NDE Workshop, July 12-14, 2010.

2. NUREG report, NUREG/CP-0189, 2003.

3. A. Baum, K. Evans, Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Salt Lake City, Utah, Aug. 1-5, 2005, p. 1155-1162.

4. EPRI Workshop on Intergranular Corrosion and Primary Water Stress Corrosion Cracking Mechanisms, NP-5971;Sarver,1987

5. M. L. Castano-Marin, D. Gomez-Briceno, F. Hernandez-Arroyo, Proc. of 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA, Aug. 1-5, 1993, p. 189-196.

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