journal article·2016-07Open access

Development of radiation damage during in-situ Kr++ irradiation of Fe Ni Cr model austenitic steels

M. Desormeaux, B. Rouxel, A.T. Motta, M. Kirk, C. Bisor, Y. de Carlan, A. Legris

Abstract

Abstract In situ irradiations of 15Cr/15Ni Ti and 15Cr/25Ni Ti model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15Ni Ti and 15Cr/25Ni Ti irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · High Temperature Alloys and Creep

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References (33)

Show source-provided references
1. Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation
2. Voids in irradiated stainless steel10.1038/216575a0 ↗
3. An overview of neutron irradiation effects in LMFBR materials
4. Theory and experimental background on dimensional changes in irradiated alloys10.1016/0022-3115(94)90009-4 ↗
5. Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling
6. Swelling of cold-worked austenitic stainless steels irradiated in HFIR under spectrally tailored conditions10.1016/S0022-3115(02)01189-3 ↗
7. Microstructural evolution in austenitic stainless steels irradiated to 57 dpa in HFIR10.1016/0022-3115(91)90138-W ↗
8. Advanced steel claddings for SFRS: feedback and challenges
9. Fe-15Ni-13Cr austenitic stainless steels for fission and fusion reactor applications. III. Phase stability during heavy ion irradiation10.1016/S0022-3115(99)00236-6 ↗
10. Overview of microstructural evolution in neutron-irradiated austenitic stainless steels10.1016/0022-3115(93)90077-C ↗
11. Radiation swelling of modified austenitic steels10.1007/s11182-008-9063-9 ↗
12. Microstructural evolution and radiation stability of steels and alloys10.1016/S0022-3115(98)00785-5 ↗
13. Radiation damage of structural materials for fast reactor fuel assembly
14. Microstructure and intergranular corrosion of the austenitic stainless steel 1.497010.1016/j.jnucmat.2006.06.010 ↗
15. Ausscheidungsverhalten des titanstabilisierten austenitischen stahls 15% Q-15% Ni-1% Mo-Ti-B (din-werkstoff-NR. 1.4970)10.1016/0022-3115(82)90454-8 ↗
16. Microstructural investigation of swelling dependence on nickel content in fast neutron-irradiated Fe-Cr-Ni austenitic ternaries10.1016/0022-3115(91)90146-X ↗
17. Synergistic effects of helium and hydrogen on self-ion-induced swelling of austenitic 18Cr10NiTi stainless steel10.1016/j.jnucmat.2013.05.022 ↗
18. Recent insights on the swelling and creep of irradiated austenitic alloys10.1016/0022-3115(84)90641-X ↗
19. A study of the effect of titanium on the void swelling behavior of D9 steels by ion beam simulation10.1016/j.jnucmat.2008.08.049 ↗
20. Egerton · 1996
21. Measurement of local thickness by electron energy-loss spectroscopy10.1016/0304-3991(87)90148-3 ↗
22. EELS log-ratio technique for specimen-thickness measurement in the TEM10.1002/jemt.1060080206 ↗
23. Thickness measurements with electron energy loss spectroscopy10.1002/jemt.20597 ↗
24. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
25. DIn situ study of heavy ion induced radiation damage in NF616 (P92) alloy10.1016/j.jnucmat.2011.08.046 ↗
26. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel10.1016/0022-3115(93)90128-L ↗
27. Stability and mobility of defect clusters and dislocation loops in metals10.1016/S0022-3115(99)00170-1 ↗
28. I. Energy calculations for pure metals10.1080/01418618708209803 ↗
29. Wand · 1995
30. Characterization of microstructure and property evolution in advanced cladding and duct: materials exposed to high dose and elevated temperature10.1557/jmr.2015.99 ↗
31. Mansur, L.K. (1987), Kinetics of nonhomogeneous processes, ed. G.R. Freeman (Wiley, New York, 1987) pp. 377-463
32. L.K. Mansur, Nucl. Technol. 40 (1978) 5.10.13182/NT78-2 ↗
33. The rate theory of swelling due to void growth in irradiated metals10.1016/0022-3115(72)90091-8 ↗