journal article·2014-10

Microstructural studies on Alloy 693

R. Halder, R.S. Dutta, P. Sengupta, I. Samajdar, G.K. Dey

Journal of Nuclear Materials· Volume 453· Issue 1-3
Publisher page

Abstract

Abstract Superalloy 693, is a newly identified ‘high-temperature corrosion resistant alloy’. Present study focuses on microstructure and mechanical properties of the alloy prepared by double ‘vacuum melting’ route. In general, the alloy contains ordered Ni 3 Al precipitates distributed within austenitic matrix. M 6 C primary carbide, M 23 C 6 type secondary carbide and NbC particles are also found to be present. Heat treatment of the alloy at 1373 K for 30 min followed by water quenching (WQ) brings about a microstructure that is free from secondary carbides and Ni 3 Al type precipitates but contains primary carbides. Tensile property of Alloy 693 materials was measured with as received and solution annealed (1323 K, 60 min, WQ) and (1373 K, 30 min, WQ) conditions. Yield strength, ultimate tensile strength (UTS) and hardness of the alloy are found to drop with annealing. It is noted that in annealed condition, considerable cold working of the alloy can be performed.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: High Temperature Alloys and Creep · Additive Manufacturing Materials and Processes · High-Temperature Coating Behaviors

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (26)

Show source-provided references
1. Ojovan · 2007
2. Kaushik · J. Nucl. Mater. · 2006 · 358 · 12910.1016/j.jnucmat.2006.07.004 ↗
3. Mishra · J. Nucl. Mater. · 2007 · 360 · 14310.1016/j.jnucmat.2006.09.012 ↗
4. Mishra · J. Am. Ceram. Soc. · 2008 · 91 · 390310.1111/j.1551-2916.2008.02773.x ↗
5. Sengupta · J. Hazard. Mater. · 2011 · 190 · 22910.1016/j.jhazmat.2011.03.031 ↗
6. Immobilization of high level nuclear wastes: the Indian scenario
7. Raj · Nucl. Eng. Des. · 2006 · 236 · 91410.1016/j.nucengdes.2005.09.036 ↗
8. Donald · 2010
9. Sengupta · J. Nucl. Mater. · 2011 · 411 · 18110.1016/j.jnucmat.2011.01.122 ↗
10. Kain · Metal. Mater. Trans. · 2005 · 36A · 107510.1007/s11661-005-0201-5 ↗
11. Sengupta · J. Nucl. Mater. · 2006 · 350 · 6610.1016/j.jnucmat.2005.11.012 ↗
12. Sengupta · J. Am. Ceram. Soc. · 2007 · 90 · 308510.1111/j.1551-2916.2007.01853.x ↗
13. Sengupta · J. Nucl. Mater. · 2008 · 374 · 18510.1016/j.jnucmat.2007.08.005 ↗
14. Sengupta · J. Nucl. Mater. · 2009 · 392 · 37910.1016/j.jnucmat.2008.07.046 ↗
15. Imrich · Ceram. Trans. · 2000 · 107 · 384
16. Bickford · J. Am. Ceram. Soc. · 1990 · 73 · 289610.1111/j.1151-2916.1990.tb06692.x ↗
17. Sengupta · J. Haz. Mater. · 2011 · 192 · 208
18. Dutta · J. Nucl. Mater. · 2013 · 432 · 7210.1016/j.jnucmat.2012.08.012 ↗
19. Hsu · Corros. Sci. · 2013 · 75 · 14810.1016/j.corsci.2013.05.027 ↗
20. Zhu · J. Nucl. Mater. · 2005 · 336 · 4710.1016/j.jnucmat.2004.08.010 ↗
21. D.F. Wilson, E.C. Beahm, T.M. Besmann, J.H. DeVan, J.R. DiStefano, U. Gat, S.R. Greene, P.L. Rittenhouse, B.A. Worley, ORNL/TM-13504, 1997.
22. Lim · J. Nucl. Mater. · 2004 · 335 · 10810.1016/j.jnucmat.2004.07.038 ↗
23. Kai · Scripta Metall. · 1989 · 23 · 1710.1016/0036-9748(89)90085-9 ↗
24. Xia · Met. Trans. A · 1990 · 21A · 2097
25. Dutta · Met. Trans. A · 2002 · 33A · 143710.1007/s11661-002-0067-8 ↗
26. Kiener · Mater. Sci. Eng. A · 2007 · 459 · 26210.1016/j.msea.2007.01.046 ↗