Evaluation of alternative alloys for PWR steam generator tubing. Final report

Technical Report · Mon Oct 01 04:00:00 EDT 1984

OSTI ID:6258256

Nelson, J L; Floreen, S

This final report summarizes the results of a project to evaluate alternative alloys for use as PWR steam generator tubing. A literature survey identified alloys 690 and 800 in the mill annealed condition and alloys 600 and 690 after annealing at 705/sup 0/C (1300/sup 0/F) for 15 hours as candidate alloys. Mill annealed alloy 600 was included as a control. C-ring tests were carried out in four secondary and one primary water environment. In the mill annealed condition, alloy 800 was more resistant to stress corrosion cracking than alloys 600 and 690. A low temperature anneal at 705/sup 0/C (1300/sup 0/F) improved the stress corrosion resistance of all the alloys. The greatest improvement was noted in alloy 690 where no failures were observed in any of the specimens even after annealing for only 4 hours. A test technique was developed to examine the stress corrosion behavior of a material by slowly internally pressurizing a section of tubing while the exterior was exposed to a simulated steam generator environment. Cracking of all alloys tested could be initiated in less than 20 days. The results indicate that alloy 600 and alloy 690 given a low temperature anneal at 705/sup 0/C (1300/sup 0/F) for 15 hours are more resistant to stress corrosion cracking than either mill annealed alloy 600 or mill annealed alloy 800. The degree of susceptibility of an alloy in this type of test may be dependent on pressurization rate.

• Research Organization: INCO Alloy Products Co. Research Center, Inc., Suffern, NY (USA)
• OSTI ID: 6258256
• Report Number(s): EPRI-NP-3703; ON: TI85920104
• Country of Publication: United States
• Language: English

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