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Radiation-Induced Segregation in Alloy X-750

  • E. A. Kenik (a1)

Abstract

The microstructural and microchemical evolution of an Alloy X-750 heat under neutron irradiation has been studied in order to understand the origin of irradiation-assisted stress corrosion cracking. Both clustering of point defects and radiation-induced segregation (RIS) at interfaces and boundaries have been observed. Although no significant changes in the precipitate structure were observed, boundaries exhibited additional depletion of Cr and Fe and enrichment of Ni.

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1. Mcllree, A.R., in Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (NACE, Houston, TX 1984), 838.
2. Bajaj, R., Mills, W.J., Lebo, M.R., Hyatt, B.Z., and Burke, M.G., in Environmental Degradation bf Materials in Nuclear Power Systems - Water Reactors (NACE, Houston, TX 1995) 1093.
3. Kenik, E.A., J. Nucl. Mater. 187, p. 239 (1992).
4. Kruger, R.M. and Was, G.S., Met. Trans. 19A, p. 2555 (1988).
5. Kenik, E.A., J. Nucl. Mater. 205, p. 317 (1993).

Radiation-Induced Segregation in Alloy X-750

  • E. A. Kenik (a1)

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