J. Mater. Sci. Technol. ›› 2021, Vol. 65: 61-71.DOI: 10.1016/j.jmst.2020.04.068
• Research Article • Previous Articles Next Articles
Ping Denga,b, Qunjia Penga,c,*(), En-Hou Hana, Wei Kea, Chen Sund
Received:
2019-12-16
Revised:
2020-03-19
Accepted:
2020-04-03
Published:
2021-02-28
Online:
2021-03-15
Contact:
Qunjia Peng
About author:
* CAS Key Laboratory of Nuclear Materials and SafetyAssessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang110016, China.E-mail addresses: pengqunjia@yahoo.com, pengqunjia@cgnpc.com.cn (Q. Peng).Ping Deng, Qunjia Peng, En-Hou Han, Wei Ke, Chen Sun. Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water[J]. J. Mater. Sci. Technol., 2021, 65: 61-71.
C | Mn | Si | S | P | Ni | Cr | Co | Fe |
---|---|---|---|---|---|---|---|---|
0.04 | 1.73 | 0.27 | 0.002 | 0.021 | 8.87 | 19.51 | 0.04 | Bal. |
Table 1 Chemical composition (wt.%) of 304NG SS.
C | Mn | Si | S | P | Ni | Cr | Co | Fe |
---|---|---|---|---|---|---|---|---|
0.04 | 1.73 | 0.27 | 0.002 | 0.021 | 8.87 | 19.51 | 0.04 | Bal. |
Fig. 2. AFM observation and analysis of the slip steps in 0.5- and 5-dpa irradiated specimens following 3% straining. (a) and (b) Typical surface topographic images of slip steps. (c) and (d) The corresponding three-dimensional morphology of the slip steps. (e) and (f) Surface height taken along the dashed line indicated in (a) and (b), respectively.
Fig. 4. Typical SEM images and EBSD analysis for 0.5- (a) and 5-dpa (b) irradiated specimens following 3% straining in simulated primary PWR water at 320 °C. (c), distribution of local misorientations obtained from (a) and (b).
Fig. 5. (a) and (b) TEM observation of the cross-section of the oxide scale formed at two slip steps with a different height in 0.5-dpa irradiated 304NG SS. (c) and (d) The corresponding EDX mappings for Cr, Fe, Ni, and O showing oxidation at surface and along the slip steps. (e) and (f) EDX point-scans collected along lines A and B shown in (b), respectively. (g) and (h) High resolution TEM observation of the inner and the oxide formed at the slip step shown in (b).
Fig. 6. (a) TEM observation of the localized corrosion at a slip step in 5-dpa irradiated 304NG SS, (b) the corresponding EDX mappings for Cr, Fe, Ni, and O showing oxidation along the slip step. (c) EDX point-scans collected along line A shown in (a). (d) High resolution TEM observation of the oxide formed at the slip step shown in (a).
Fig. 8. TEM observation of the localized corrosion at a grain boundary in SA (a), 0.5- (b) and 5-dpa (c) irradiated 304NG SS. (d), (e) and (f) the corresponding EDX mappings for Cr, Fe, Ni, and O showing oxidation along the grain boundary shown in (a), (b) and (c), respectively. (g), (h) and (i) EDX point-scans collected along lines A, B and C shown in (a), (b) and (c), respectively.
Fig. 9. (a) Depth of intergranular oxide in strain-free and 3% strained specimens as a function of irradiation dose. Each of the bars in the dose columns represents an analyzed grain boundary at the corresponding dose level. (b) Dependence of average depth of intergranular oxidation on irradiation dose.
Fig. 10. SEM observation of surface cracking of 304NG SS subjected to different irradiation doses following a strain of 1% (left) and 3% (right) in simulated primary PWR water at 320 °C. (a, b) solution annealed, (c, d) 0.5 dpa, (e, f) 1.5 dpa, (g, h) 5 dpa. (g) and (h) were imaged from the same location for the purpose of the correlation between the applied strain and cracking initiation.
Fig. 11. (a) SEM observation of intragranular cracking at slip step in 1.5-dpa irradiated 304NG SS following a strain of 3% in simulated primary PWR water at 320 °C. (b)High magnification SEM images of the selected region A in (a).
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