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

Jiwei Lin1,2, Tianyi Hu3, Xu Yu3

  • 1Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai 200233, China.

Materials (Basel, Switzerland)
|February 27, 2026
PubMed
Summary

Neutron irradiation causes defects in Inconel 617 (IN617). Interstitials form large clusters, while vacancies stay isolated, leading to dislocation loops and hardening in advanced nuclear materials.

Keywords:
Inconel 617 alloydefect evolutionheat pipe-cooled reactorirradiation damagemolecular dynamics

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Area of Science:

  • Materials Science
  • Nuclear Engineering
  • Computational Physics

Background:

  • Inconel 617 (IN617) is a key material for advanced nuclear systems like heat pipe-cooled reactors.
  • Understanding its behavior under neutron irradiation is crucial for reactor safety and performance.

Purpose of the Study:

  • To investigate the atomic-scale mechanisms of irradiation damage in IN617.
  • To elucidate defect evolution pathways under neutron irradiation using molecular dynamics simulations.

Main Methods:

  • Classical molecular dynamics simulations were employed.
  • Simulated successive displacement cascades in a Ni-Cr-Co ternary model of IN617.

Main Results:

  • Frenkel pair accumulation showed a near-linear relationship with radiation dose.
  • A significant asymmetry in defect behavior was observed: interstitials clustered, while vacancies remained isolated.
  • Interstitial clustering led to dislocation loop nucleation and a rise in dislocation density.

Conclusions:

  • Irradiation hardening in IN617 is predominantly driven by interstitial-type defect clustering.
  • These findings provide a mechanistic understanding for IN617 performance in radiation environments.
  • The study offers critical insights for the design and safety assessment of advanced nuclear reactors utilizing IN617.