Neutron defect emulation using ion beam in zircaloy-4
Abstract
The present study is devoted to study ion beam induced defects in zircaloy-4. We focused on the effect on the surface morphology modifications. The samples are first polished and then bombarded with 20 MeV Au ion and 0.7 MeV Cu ion at room temperature to a dose of 4.5 dpa. After irradiation the samples were subjected to chemical etching in 47 ml nitric acid (HNO3), 3 ml hydrofluoric acid (HF) and 50 ml water (H2O). Optical microscopy observation showed drastic changes in the microstructure after irradiation. The observation at the interface between the irradiated part and non-irradiated part revealed a clear shrinkage parallel to the ion beam direction. Fine grain of about 10 µm diameter are formed on the surface of zircaloy-4 irradiated at low energy (Sn/Se << 1) while a hillocks-like nanostructure is observed in the case of high energy irradiation (Sn/Se >> 1). Both cases can affect the zircaloy-4 corrosion resistance.
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2. Arjhangmehr A, Feghhi SAH. Irradiation deformation near different atomic grain boundaries in α-Zr: An investigation of thermodynamics and kinetics of point defects. Sci Rep. 2016;6:23333. doi: 10.1038/srep23333.
3. Raquel ML, Arnaldo HPA. Influence of neutron irradiation on the stability of the precipitates in zircaloy- A critical review. In: International Nuclear Atlantic Conference - INAC 2013; 2013; Recife, PE, Brazil.
4. Adamson R, Griffiths M, Patterson C. Irradiation Growth of Zirconium Alloys: A Review. 2017. Advanced Nuclear Technology International, Tollered, Sweden. Available from: https://www.antinternational.com/docs/samples/FM/04/ZIRAT22-IZNA17_Irradiation_Growth_of_Zirconium_Alloys_Sample.pdf
5. Buckley SN. Properties of Reactor Materials and the Effects of Irradiation Damage. London: Butterworths; 1961. p. 443. Buckley SN. Irradiation Growth in Properties of Reactor Materials and Effects on Radiation Damage. In: Littler DJ, editor. London: Butterworth; 1962. p. 413.
6. Kelly PM. Irradiation Growth in Zirconium. In: International Conference of Physical Metallurgy of Reactor Fuel Elements; 1973; Berkeley Nuclear Laboratories, UK.
7. Nichols EA. Radiation Enhanced Creep. In: Radiation Damage in Metals. Metals Park, OH: American Society for Metals; 1976. p. 267-94.
8. Li Y, Ghoniem N. Cluster dynamics modeling of irradiation growth in single crystal Zr. J Nucl Mater. 2020;540:152312.
9. Carpenter GJC, Murgatroyd RA, Rogerson A, Watters JF. Irradiation growth of zirconium single crystals. J Nucl Mater. 1988;101:28-37.
10. Rogerson A. Irradiation growth in annealed and 25% cold-worked zircaloy-2 between 353-673 K. J Nucl Mater. 1988;154:276-85.
11. Cazado ME, Goldberg E, Togneri MA, Denis A, Soba A. A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code. Nucl Eng Des. 2021;373:111009.
12. Cai J, Guan QF, Lv P, Zhang C, Yin Y. Crater Formation on the Surface of Pure Metal and Alloy Irradiated by High Current Pulsed Electron Beam. High Temp Mater Proc. 2018;37(8):777-84.
13. Ziegler JF, Biersack JP, Littmark U. The Stopping and Range of Ions in Solids. New York: Pergamon; 1985. Available from: http://srim.org/
14. Hengstler-Eger RM, Baldo P, Beck L, Dorner J, Ertl K, Hoffmann PB, et al. Heavy ion irradiation induced dislocation loops in AREVA’s M5Ò alloy. J Nucl Mater. 2012;423:170-82.
15. Adamson RB, Coleman CE, Griffiths M. Irradiation creep and growth of zirconium alloys: A critical review. J Nucl Mater. 2019;521:167-244.
16. Han ZY, Ji L, Cai, Zou H, Wang ZP, Guan QF. Surface Nanocrystallization of 3Cr13 Stainless Steel Induced by High-Current Pulsed Electron Beam Irradiation. J Nanomater. 2013;603586:603586.
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