TY - JOUR
T1 - Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium
AU - Gabriel, Adam
AU - Hawkins, Laura
AU - French, Aaron
AU - Li, Yongchang
AU - Hu, Zhihan
AU - He, Lingfeng
AU - Xiu, Pengyuan
AU - Nastasi, Michael
AU - Garner, Frank A.
AU - Shao, Lin
N1 - Funding Information:
The structural characterization was supported by the Nuclear Science User Facility (NSUF) under the Rapid Turnaround Experiment (RTE) FY2019 through project 1799. The work was supported by Triad National Security, LLC , through LANL-TAMU Triad Program project M2101345–01–00001 .
Publisher Copyright:
© 2022 Elsevier B.V.
PY - 2022/4/1
Y1 - 2022/4/1
N2 - Pure chromium is a promising candidate for coating of Zircalloy fuel rods in light water-cooled power reactors to avoid or delay hydrogen generation in accident scenarios. Void swelling of chromium is one possible contributor to coating-interface failure and needs to be studied. The effect of dpa rate on void swelling of Cr was studied using 5 MeV Fe ion irradiation to 15 peak dpa at peak dpa rates of 3.5 × 10−5, 3.5 × 10−4, and 3.5 × 10−3 dpa/s, at six temperatures between 350 °C and 650 °C. The post-transient (steady-state) swelling rate of pure Cr is ∼0.05%/dpa. Swelling in Cr also appeared to start at a much higher swelling rate at very low doses. The observed dependence of peak swelling temperature on dpa rate agrees well with earlier theoretical models and clearly demonstrated the well-known “temperature shift” phenomenon. After determination of the peak swelling temperatures under ion irradiation at three dpa rates we extrapolated downwards to dpa rates characteristic of both sodium-cooled fast reactors and light water-cooled reactors.
AB - Pure chromium is a promising candidate for coating of Zircalloy fuel rods in light water-cooled power reactors to avoid or delay hydrogen generation in accident scenarios. Void swelling of chromium is one possible contributor to coating-interface failure and needs to be studied. The effect of dpa rate on void swelling of Cr was studied using 5 MeV Fe ion irradiation to 15 peak dpa at peak dpa rates of 3.5 × 10−5, 3.5 × 10−4, and 3.5 × 10−3 dpa/s, at six temperatures between 350 °C and 650 °C. The post-transient (steady-state) swelling rate of pure Cr is ∼0.05%/dpa. Swelling in Cr also appeared to start at a much higher swelling rate at very low doses. The observed dependence of peak swelling temperature on dpa rate agrees well with earlier theoretical models and clearly demonstrated the well-known “temperature shift” phenomenon. After determination of the peak swelling temperatures under ion irradiation at three dpa rates we extrapolated downwards to dpa rates characteristic of both sodium-cooled fast reactors and light water-cooled reactors.
UR - https://www.scopus.com/pages/publications/85123371456
UR - https://www.mendeley.com/catalogue/63c219dc-234c-3dcf-954a-d7773ea58854/
U2 - 10.1016/j.jnucmat.2022.153519
DO - 10.1016/j.jnucmat.2022.153519
M3 - Article
AN - SCOPUS:85123371456
SN - 0022-3115
VL - 561
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153519
ER -