Integrated Modeling of Second Phase Precipitation in Cold-Worked 316 Stainless Steels under Irradiation

TL;DR

This study develops an integrated model combining Cluster Dynamics and CALPHAD techniques to predict second phase precipitation in cold-worked 316 stainless steels under irradiation, aligning well with experimental data and offering insights for nuclear reactor applications.

Contribution

The paper introduces a novel integrated modeling approach that combines radiation effects and thermodynamic precipitation modeling for irradiated stainless steels.

Findings

Accurately predicts gamma-prime (Ni3Si) precipitation evolution under fast reactor conditions.

Shows carbide volume fraction is higher in LWR conditions than in fast reactors, indicating flux effects.

Provides quantitative predictions of precipitate volume fractions under extended reactor life conditions.

Abstract

The current work combines the Cluster Dynamics (CD) technique and CALPHAD-based precipitation modeling to address the second phase precipitation in cold-worked (CW) 316 stainless steels (SS) under irradiation at 300-400 C. CD provides the radiation enhanced diffusion and dislocation evolution as inputs for the precipitation model. The CALPHAD-based precipitation model treats the nucleation, growth and coarsening of precipitation processes based on classical nucleation theory and evolution equations, and simulates the composition, size and size distribution of precipitate phases. We benchmark the model against available experimental data at fast reactor conditions (9.4 x 10^-7 dpa/s and 390 C) and then use the model to predict the phase instability of CW 316 SS under light water reactor (LWR) extended life conditions (7 x 10^-8 dpa/s and 275 C). The model accurately predicts the gamma-prime (Ni3Si) precipitation evolution under fast reactor conditions and that the formation of this phase is dominated by radiation enhanced segregation. The model also predicts a carbide volume fraction that agrees well with available experimental data from a PWR reactor but is much higher than the volume fraction observed in fast reactors. We propose that radiation enhanced dissolution and/or carbon depletion at sinks that occurs at high flux could be the main sources of this inconsistency. The integrated model predicts ~1.2% volume fraction for carbide and ~3.0% volume fraction for gamma-prime for typical CW 316 SS (with 0.054 wt.% carbon) under LWR extended life conditions. This work provides valuable insights into the magnitudes and mechanisms of precipitation in irradiated CW 316 SS for nuclear applications.