# Molecular Dynamics Study of Defect Evolution in Inconel 617 Alloy Under Successive Cascade Irradiation

**Authors:** Jiwei Lin, Tianyi Hu, Xu Yu, Hai Huang, Yang Ding, Junqiang Lu

PMC · DOI: 10.3390/ma19040732 · 2026-02-13

## TL;DR

This study uses simulations to explore how radiation damage accumulates in Inconel 617 alloy at the atomic level, revealing how defects evolve and affect material properties.

## Contribution

The study reveals the asymmetric behavior of interstitial and vacancy defects under irradiation, and how interstitial clustering drives dislocation loop formation in Inconel 617.

## Key findings

- Frenkel pair accumulation increases linearly with irradiation dose.
- Interstitials form large clusters while vacancies remain isolated.
- Dislocation density rises linearly and reaches a saturation point.

## Abstract

Inconel 617 (IN617) is a promising structural material for advanced nuclear systems such as heat pipe-cooled reactors, but its fundamental defect evolution under neutron irradiation remains poorly understood. This study employs classical molecular dynamics simulations to investigate the atomic-scale irradiation damage mechanisms in a representative Ni–Cr–Co ternary model of IN617 under successive displacement cascades. The results reveal a near-linear accumulation of Frenkel pairs with dose, with the count increasing by a factor of approximately 24 from the first to the 75th cascade. A critical finding is the stark asymmetry in defect kinetics: interstitials rapidly coalesce into large clusters (with 88.4% of interstitials found in clusters of ≥ 2 atoms after 75 cascades), while vacancies remain predominantly isolated (constituting 68.8% of all vacancy defects). This disparity directly governs microstructural evolution, as interstitial cluster growth drives dislocation loop nucleation, leading to a linear rise in dislocation density to a saturated value of approximately 4.5 × 10−4 Å−2. The saturated dislocation structure subsequently undergoes continuous reorganization through reactions between partial dislocations. These insights demonstrate that irradiation hardening in IN617 under simulated conditions is governed primarily by interstitial-type defect clustering, providing a crucial mechanistic basis for assessing its performance in radiation environments.

## Full-text entities

- **Diseases:** injury to (MESH:D014947), Dislocation (MESH:D004204)
- **Chemicals:** Ni (MESH:D009532), hydrogen (MESH:D006859), Co (MESH:D003035), Cr (MESH:D002857), Tm (MESH:D013932), Hastelloy N alloy (-), Zr (MESH:D015040)
- **Species:** Homo sapiens (human, species) [taxon 9606]

## Figures

5 figures with captions in the complete paper: https://tomesphere.com/paper/PMC12941984/full.md

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Source: https://tomesphere.com/paper/PMC12941984