Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen
Source abstract
Abstract
Abstract In recent years, it has been observed that Inconel X-750 spacers in CANDU reactors exhibits lower ductility with reduced load carrying capacity following irradiation in a reactor environment. The fracture behaviour of ex-service material was also found to be entirely intergranular at high doses. The thermalized flux spectrum in a CANDU reactor leads to transmutation of 58 Ni to 59 Ni. The 59 Ni itself has unusually high thermal neutron reaction cross-sections of the type: ( n , γ ), ( n , p ), and ( n , α ). The latter two reactions, in particular, contribute to a significant enhancement of the atomic displacements in addition to creating high concentrations of hydrogen and helium within the material. Microstructural examinations by transmission electron microscopy (TEM) have confirmed the presence of helium bubbles in the matrix and aligned along grain boundaries and matrix–precipitate interfaces. Helium bubble size and density are found to be highly dependent on the irradiation temperature and material microstructure; the bubbles are larger within grain boundary precipitates. TEM specimens extracted from fracture surfaces and crack tips provide information that is consistent with crack propagation along grain boundaries due to the presence of He bubbles.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (21)
Show source-provided references
1. Embrittlement of Nickel Alloys in a Candu∗ Reactor Environment
2. The microstructure of unirradiated and neutron irradiated Inconel X-750
3. Mansur · J. Nucl. Mater. · 1993 · 206 · 30610.1016/0022-3115(93)90130-Q ↗
4. Enhancement of irradiation creep of nickel-bearing alloys in thermalized neutron spectra characteristic of Lwr and Candu Reactors
5. D.G. Doran, N.J. Graves, ASTM, 1976, STP 611, pp. 564–482.
6. Norgett · Nucl. Eng. Des. · 1975 · 33 · 5010.1016/0029-5493(75)90035-7 ↗
7. Farrar · J. Vac. Sci. Technol. · 1989 · 1740
8. F. Garner, L.R. Greenwood, B.M. Oliver, in: A Re-Evaluation of Helium/Dpa and Hydrogen/Dpa Ratios for Fast Reactor and Thermal Reactor Data Used in Fission-Fusion Correlations, Proceedings of a Technical Committee meeting held in Obnisk, Russian Federation, 16–19 June 1997; 1997.10.2172/414892 ↗
9. Greenwood · J. Nucl. Mater. · 1996 · 233–237 · 153010.1016/S0022-3115(96)00264-4 ↗
10. Greenwood · J. ASTM Int. · 2004 · 110.1520/JAI11365 ↗
11. Greenwood · J. Nucl. Mater. · 1983 · 115 · 13710.1016/0022-3115(83)90302-1 ↗
12. Bickel · J. Nucl. Mater. · 2002 · 306 · 2110.1016/S0022-3115(02)01230-8 ↗
13. Edwards · J. Nucl. Mater. · 2009 · 384 · 24910.1016/j.jnucmat.2008.11.025 ↗
14. G.A. Young, N. Lewis, M. Hanson, W. Matuszyk, B. Wiersma, S.C. Gonzalez, KAPL Report LM-01K034; Microstructurat and Microchemical Characterization of Dual Step Aged Alloy X-750 and Its Relationship to Environmentally Assisted Cracking; May 2001.10.2172/821679 ↗
15. Hasegawa · 1979 · vol. 65
16. Williams, D.B. and Carter, C.B., Transmission Electron Microscopy. New York, vol. 3, 1996.10.1007/978-1-4757-2519-3_1 ↗
17. Egerton · 2011
18. Fréchard · J. Nucl. Mater. · 2009 · 393 · 10210.1016/j.jnucmat.2009.05.011 ↗
19. Yang · J. Nucl. Mater. · 1985 · 132 · 24910.1016/0022-3115(85)90370-8 ↗
20. Rowcliffe · J. Nucl. Mater. · 2009 · 392 · 34110.1016/j.jnucmat.2009.03.023 ↗
21. Grove, C.A. and Petzold, L.D. In Mechanisms of Stress Corrosion Cracking of Alloy X-750 in High Purity Water, International Conference on Corrosion of Nickel Base Alloys, Cincinnati, Ohio, Octobter 23–25, 1984; ASM: Cincinnati, Ohio, 1985.10.1007/BF02833560 ↗