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Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

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Abstract

A commercial purity 304SS was irradiated to 5 dpa Kinchin-Pease (10 dpa full-cascade) using 2 meV protons at 360 °C. Post-irradiation annealing (PIA) was applied to reduce or remove IASCC susceptibility. This paper focuses on the links between irradiation-induced hardening and irradiated microstructures of the as-irradiated and PIA conditions; the irradiated microstructure is assessed by transmission electron microscopy (TEM) and atom probe tomography (APT) . Dislocation loops, Ni–Si clusters, and Cu-enriched clusters are present in the as-irradiated condition. When the dislocation loops are removed by PIA, ~40% of the as-irradiated hardness remains and can be rationally attributed to the solute clusters still present in the PIA microstructure. The observations indicate that hardening in the as-irradiated condition is controlled by both dislocation loops and solute clusters and suggest that radiation-induced solute clusters may be important to detailed understanding of IASCC (irradiation-assisted stress corrosion cracking) .

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Notes

  1. 1.

    There are two options in SRIM for calculations of dose: “full-cascade” and “Kinchin-Pease.” A large number of studies across the years that applied proton-irradiation to investigate radiation damage calculated dose using the full-cascade option. However, a recent publication by Stoller et al. [22] established that the Kinchin-Pease option is more appropriate when comparing ion and neutron displacement damage. The Kinchin-Pease (K-P) value is a factor of 2 less than the full-cascade value; that is, 10 dpa (full-cascade) corresponds to 5 dpa (K-P).

  2. 2.

    The aggressiveness of post-irradiation annealing condition is captured by the parameter √DFet, the “iron diffusion distance” [16].

  3. 3.

    Toyama et al. reported two types of Ni/Si clusters, one that contained Mn and P and another that contained neither. However, they did not draw a distinction between the two populations in subsequent analysis.

  4. 4.

    Because of cluster/loop ratio they measured (loops by TEM and solute clusters by APT) was high, Toyama et al. “strongly suggested that Ni–Si precipitates mainly exist at sites independent of Frank loops”, although the suggestion was not directly verified by APT observation. In our study, the average linear density of Ni-rich clusters (actually Ni/Si rich clusters) on dislocations was determined by APT to be 12 clusters per 100 nm; and the cluster/loop ratio of proton-irradiated CP304 (14.6) is, in fact, higher than that measured by Toyama et al. for neutron-irradiated 304SS (6.9). In proton-irradiated CP304, the average dislocation loop diameter 9.4 nm according to APT (Table 3) [or 7.4 nm according to TEM (Table 2)]. Therefore, there are ~3.5 clusters are associated with the average dislocation loop. It follows that approximately (3.5/14.6) × 100% = 24% of the clusters are associated with dislocation loops, while the majority, ~76%, are “free clusters”.

  5. 5.

    In this paper, “clusters” and “precipitates” will be used interchangeably.

  6. 6.

    The model also does not account for any changes in hardness associated with the loss of solution hardening in the matrix when solutes are removed from the matrix to form clusters/precipitates.

  7. 7.

    Converted according to the empirical relation Δσy = 3.03 ΔHv [36].

  8. 8.

    An exact percentage contribution is difficult to provide because of the root-mean-square summation of the contributions of Frank loop and clusters.

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Acknowledgements

The work presented in this paper was funded by the Electric Power Research Institute.

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Author notes

  1. Yimeng Chen

    Present address: CAMECA Instruments, Inc, Madison, WI, 53711, USA

Authors and Affiliations

  1. Department of Materials Science and Engineering, University of Michigan, Ann Arbor, MI, 48109, USA

    Yimeng Chen, Yan Dong & Emmanuelle Marquis

  2. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI, 48109, USA

    Zhijie Jiao, Justin Hesterberg & Gary Was

  3. Electric Power Research Institute, Palo Alto, CA, 94304, USA

    Peter Chou

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  1. Yimeng Chen
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Correspondence to Peter Chou .

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Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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Chen, Y. et al. (2019). Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_147

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