Corrosion inhibition of steam generator tubesheet by Alloy 690 cladding in secondary side environments
Source abstract
Abstract
Abstract Denting is a phenomenon that a steam generator tube is distorted by a volume expansion of corrosion products of the tube support and tubesheet materials adjacent to the tube. Although denting has been mitigated by a modification of the design and material of the tube support structures, it has been an inevitable concern in the crevice region of the top of tubesheet. This paper provides a new technology to prevent denting by cladding the secondary surface of the tubesheet with a corrosion resistant material. In this study, Alloy 690 material was cladded onto the surface of an SA508 tubesheet to a thickness of about 9 mm. The corrosion rates of the original SA508 tubesheet and the Alloy 690 clad material were measured in acidic and alkaline simulated environments. Using Alloy 690 cladding, the corrosion rate of the tubesheet within a magnetite sludge pile decreased by a factor of 680 in 0.1 M NiCl2 solution at 300 °C, and by a factor of 58 in 2 M NaOH solution at 315 °C. This means that denting can drastically be prevented by cladding the secondary tubesheet surface with corrosion resistant materials.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (13)
Show source-provided references
1. Tube support and tubesheet corrosion
2. Staehle · Corrosion · 2003 · 59 · 93110.5006/1.3277522 ↗
3. Diercks · Nucl. Eng. Des. · 1999 · 194 · 1910.1016/S0029-5493(99)00167-3 ↗
4. Broomfield · 1986
5. Assessment and management of ageing of major nuclear plant components important to safety: steam generators, IAEA-TECDOC-1668, IAEA, 2011.
6. H.M. Feldman, Steam generator life management roadmap, in: Proceeding of SGMP KHNP/EPRI, Workshop, 2011, pp. 93–112.
7. J. Cook, D. Lynch, M. Shields, The use of the D-probe for TTS dent characterization at Ginna, in: 30th EPRI Steam Generator NDE Workshop, Seattle (USA), July 18–20, 2011.
8. Tsuda · 2000
9. S. Odar, Water chemistry measures to improve steam generator performance, in: Proceedings of the 14th International Conference on the Properties of Water and Steam in Kyoto, 2004, pp. 531–538.
10. Fruzzetti · 2009
11. Fontana · 1984
12. Lian · 2010
13. USNRC Letter ML-093280169, Fort Calhoun Station Unit 1 – review of the 2008 refueling outage steam generator tube inservice inspection report (TAC No. ME0313), USNRC, November 25, 2009.