Irradiation-induced swelling of pure chromium with 5 MeV Fe ions in the temperature range 450-650 °C

JOURNAL OF NUCLEAR MATERIALS

卷:543

Article

Ryabikovskaya, Ekaterina¹  French, Aaron¹  Gabriel, Adam¹  Kim, Hyosim²  Wang, Tianyao¹  Shirvan, Koroush³  Garner, Frank A.¹  Shao, Lin¹ 

[1] Texas A&M Univ, Dept Nucl Engn, College Stn, TX 77843 USA

[2] Los Alamos Natl Lab, Los Alamos, NM 87545 USA

[3] MIT, Dept Nucl Sci & Engn, Cambridge, MA 02139 USA

关键词: Chromium;    Void swelling;    Accident tolerant fuel cladding;    Ion irradiation;    Void superlattice;   

DOI  :  10.1016/j.jnucmat.2020.152585

来源: Elsevier

【 摘 要 】

A surface coating using pure chromium has been proposed to increase the accident tolerance of Zircaloy cladding in pressurized water reactors. However, there is not much irradiation experience with Cr alloys and especially pure Cr. In the present study, pure chromium was irradiated with 5 MeV Fe ions to 50 peak dpa (displacements per atom) at temperatures of 450, 500, 550, 600 and 650 degrees C. Then irradiation at the peak swelling temperature of 550 degrees C was conducted to 50, 100, 150 peak dpa. Swelling at 50 dpa was observed over the entire temperature range studied, 450-650 degrees C, but appeared to be decreasing strongly at the temperature boundaries of the experiment. After an initial transient of rapid swelling, chromium was observed to swell at a rate of similar to 0.03-0.04%/dpa (up to 120 local dpa), which is much lower than pure Fe at 0.2%/dpa. This low swelling rate was found to be relatively insensitive to dpa rate, which varied by a factor of similar to 2 over the depth of data collection. Swelling was observed to begin quickly with an incubation period less than 10 dpa. Self-organization in the form of void ordering was observed to be developing at 50 dpa, becoming better defined with increasing dose. The void alignment direction is determined to be the (111) axial direction. (C) 2020 Elsevier B.V. All rights reserved.

【 授权许可】

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