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Citation: G. Bonny, N. Castin, and D. Terentyev (2013), "Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy", Modelling and Simulation in Materials Science and Engineering, 21(8), 85004. DOI: 10.1088/0965-0393/21/8/085004.
Abstract: The degradation of austenitic stainless steels in a radiation environment is a known problem for the in-core components of nuclear light water reactors. For a better understanding of the prevailing mechanisms responsible for the materials' degradation, large-scale atomistic simulations are desirable. In this framework and as a follow-up on Bonny et al (2011 Modelling Simul. Mater. Sci. Eng. 19 085008), we developed an embedded atom method type interatomic potential for the ternary FeNiCr system to model the production and evolution of radiation defects. Special attention has been drawn to the Fe10Ni20Cr alloy, whose properties were ensured to be close to those of 316L austenitic stainless steels. The potential is extensively benchmarked against density functional theory calculations and the potential developed in our earlier work. As a first validation, the potential is used in AKMC simulations to simulate thermal annealing experiments in order to determine the self-diffusion coefficients of the components in FeNiCr alloys around the Fe10Ni20Cr composition. The results from these simulations are consistent with experiments, i.e., DCr > DNi > DFe.

Notes: Notes from Giovanni Bonny: "The present potential was developed to model POINT DEFECTS near the Fe-10Ni-20Cr composition.

LAMMPS pair_style eam/alloy (2013--Bonny-G--Fe-Ni-Cr--LAMMPS--ipr1)
Notes: This file was provided by Giovanni Bonny (Nuclear Materials Science Institute of SCK-CEN, Belgium) on 13 Jan. 2014.
File(s):
EAM tabulated functions
Citation: G. Bonny, D. Terentyev, R.C. Pasianot, S. Poncé, and A. Bakaev (2011), "Interatomic potential to study plasticity in stainless steels: the FeNiCr model alloy", Modelling and Simulation in Materials Science and Engineering, 19(8), 85008. DOI: 10.1088/0965-0393/19/8/085008.
Abstract: Austenitic stainless steels are commonly used materials for in-core components of nuclear light water reactors. In service, such components are exposed to harsh conditions: intense neutron irradiation, mechanical and thermal stresses, and aggressive corrosion environment which all contribute to the components' degradation. For a better understanding of the prevailing mechanisms responsible for the materials degradation, large-scale atomistic simulations are desirable. In this framework we developed an embedded atom method type interatomic potential for the ternary FeNiCr system to model movement of dislocations and their interaction with radiation defects. Special attention has been drawn to the Fe-10Ni-20Cr alloy, whose properties were ensured to be close to those of 316L austenitic stainless steel. In particular, the stacking fault energy and elastic constants are well reproduced. The fcc phase for the Fe–10Ni-20Cr random alloy was proven to be stable in the temperature range 0–900 K and under shear strain up to 5%. For the same alloy the stable glide of screw dislocations and stability of Frank loops was confirmed.

Notes: Notes from Giovanni Bonny: "The present potential was developed to model dislocations around the Fe-10Ni-20Cr composition."

LAMMPS pair_style eam/alloy (2011--Bonny-G--Fe-Ni-Cr--LAMMPS--ipr1)
Notes: This file was provided by Giovanni Bonny (Nuclear Materials Science Institute of SCK-CEN, Belgium) on 2 Sept. 2013.
File(s):
EAM tabulated functions
Notes: These files were provided by Giovanni Bonny on 2 Sept. 2013.
File(s):
Date Created: October 5, 2010 | Last updated: October 05, 2018