skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Multi-scale simulation of radiation damage accumulation and subsequent hardening in neutron-irradiated α-Fe

Journal Article · · Modelling and Simulation in Materials Science and Engineering
 [1];  [2];  [3]
  1. Georgia Inst. of Technology, Georgia Tech., Metz (France); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  3. Georgia Inst. of Technology, Georgia Tech., Metz (France)

A hierarchical methodology is introduced to predict the effects of radiation damage and irradiation conditions on the yield stress and internal stress heterogeneity developments in polycrystalline α-Fe. Simulations of defect accumulation under displacement cascade damage conditions are performed using spatially resolved stochastic cluster dynamics. The resulting void and dislocation loop concentrations and average sizes are then input into a crystal plasticity formulation that accounts for the change in critical resolved shear stress due to the presence of radiation induced defects. The simulated polycrystalline tensile tests show a good match to experimental hardening data over a wide range of irradiation doses. With this capability, stress heterogeneity development and the effect of dose rate on hardening is investigated. The model predicts increased hardening at higher dose rates for low total doses. By contrast, at doses above 10–2 dpa when cascade overlap becomes significant, the model does not predict significantly different hardening for different dose rates. In conclusion, the development of such a model enables simulation of radiation damage accumulation and associated hardening without relying on experimental data as an input under a wide range of irradiation conditions such as dose, dose rate, and temperature.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC04-94AL85000
OSTI ID:
1258477
Alternate ID(s):
OSTI ID: 1239006
Report Number(s):
SAND-2015-10308J; 642139
Journal Information:
Modelling and Simulation in Materials Science and Engineering, Vol. 24, Issue 1; ISSN 0965-0393
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 26 works
Citation information provided by
Web of Science

References (65)

Crystal plasticity-based constitutive modelling of irradiated bcc structures journal March 2012
Irradiation hardening in copper and nickel journal October 1960
Irradiation-induced microstructural changes, and hardening mechanisms, in model PWR reactor pressure vessel steels journal August 1995
Radiation hardening of copper single crystals journal December 1960
Influence of irradiation parameters on damage accumulation in metals and alloys journal November 1994
Dislocation density-based constitutive model for the mechanical behaviour of irradiated Cu journal December 2004
Analysis of Obstacle Hardening Models Using Dislocation Dynamics: Application to Irradiation-Induced Defects journal May 2015
Interaction of carbon with vacancy and self-interstitial atom clusters in α-iron studied using metallic–covalent interatomic potential journal January 2011
Elastic interaction between prismatic dislocation loops and straight dislocations journal January 1964
Evolution of point defect clusters in pure iron under low-energy He+ irradiation journal May 2001
Irradiation hardening behavior of polycrystalline metals after low temperature irradiation journal March 2004
Effect of irradiation temperature and dose on radiation hardening of some pure metals journal October 2011
Microstructural evolution in Fe and Fe–Cr model alloys after He+ ion irradiations journal August 2004
Microstructure of neutron-irradiated iron before and after tensile deformation journal June 2006
Voids in Irradiated Stainless Steel journal November 1967
Hybrid Monte Carlo Simulation of Stress-Induced Texture Evolution with Inelastic Effects journal November 2010
Formation of stable sessile interstitial complexes in reactions between glissile dislocation loops in bcc Fe journal December 2008
Spatially resolved stochastic cluster dynamics for radiation damage evolution in nanostructured metals journal November 2013
Simulation of the nanostructure evolution under irradiation in Fe–C alloys journal November 2013
Atomic-scale mechanisms of void hardening in bcc and fcc metals journal March 2010
Simulating radiation damage accumulation in α -Fe: A spatially resolved stochastic cluster dynamics approach journal May 2015
Clear band formation simulated by dislocation dynamics: Role of helical turns and pile-ups journal October 2008
A polycrystal plasticity model of strain localization in irradiated iron journal February 2013
A polycrystalline modeling of the mechanical behavior of neutron irradiated zirconium alloys journal February 2009
A novel method for computing effective diffusivity: Application to helium implanted α-Fe thin films journal May 2014
Continuum modeling of localized deformation in irradiated bcc materials journal January 2013
A review of irradiation assisted stress corrosion cracking journal August 1994
The Displacement of Atoms in Solids by Radiation journal January 1955
Method for the Calculation of DPA in the Reactor Pressure Vessel of Atucha II journal January 2011
A new algorithm for Monte Carlo simulation of Ising spin systems journal January 1975
Modeling and simulation of irradiation hardening in structural ferritic steels for advanced nuclear reactors journal June 2008
The theoretical behavior of a polycrystalline solid as related to certain general concepts of continuum plasticity journal March 1969
Transfer of molecular dynamics data to dislocation dynamics to assess dislocation–dislocation loop interaction in iron journal October 2013
Radiation induced precipitation in nickel silicon solid solutions: Dose rate effects journal September 1977
The effect of interstitial impurities on radiation hardening and embrittlement in iron journal October 1966
Stochastic cluster dynamics method for simulations of multispecies irradiation damage accumulation journal August 2011
Computer simulation of reactions between an edge dislocation and glissile self-interstitial clusters in iron journal September 2006
CXXX. On the linear work hardening mate of face-centred cubic single crystals journal November 1955
Work-hardening and work-softening of face-centred cubic metal crystals journal March 1957
Dependence of irradiation creep on temperature and atom displacements in 20% cold worked type 316 stainless steel journal March 1977
A stochastic approach to capture crystal plasticity journal September 2011
Multiscale modelling of defect kinetics in irradiated iron journal December 2004
Dislocation loop growth in pure iron under electron irradiation journal August 1989
The effect of dislocation self-interaction on the orowan stress journal December 1973
A size-dependent tensorial plasticity model for FCC single crystal with irradiation journal February 2015
Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys journal May 2014
Migration kinetics of the self-interstitial atom and its clusters in bcc Fe journal February 2001
A general method for numerically simulating the stochastic time evolution of coupled chemical reactions journal December 1976
The mechanism of climb in dislocation–nanovoid interaction journal May 2012
Atomistically informed crystal plasticity model for body-centered cubic iron journal May 2012
Operating temperature windows for fusion reactor structural materials journal November 2000
Radiation hardening revisited: role of intracascade clustering journal October 1997
Dose dependence of defect accumulation in neutron irradiated copper and iron journal December 2002
The microstructure and associated tensile properties of irradiated fcc and bcc metals journal January 2000
The evolution of mechanical property change in irradiated austenitic stainless steels journal November 1993
The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulations journal January 2000
Statistical analysis of a library of molecular dynamics cascade simulations in iron at 100 K journal December 2000
Analysis of displacement damage and defect production under cascade damage conditions journal February 1993
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel journal November 1993
Story of stacking fault tetrahedra journal September 1997
Similarity and difference between fcc, bcc and hcp metals from the view point of point defect cluster formation journal January 2000
Atomic displacement processes in irradiated metals journal October 1994
The role of cascade energy and temperature in primary defect formation in iron journal January 2000
Development of mechanical property correlation methodology for fusion environments journal December 1979
Dependence of Irradiation Creep on Temperature and Atom Displacements in 20% Cold Worked Type 316 Stainless Steel
  • Gilbert, E. R.; Bates, J. F.
  • Measurement of Irradiation-enhanced Creep in Nuclear Materials: Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976 https://doi.org/10.1016/b978-0-7204-0572-9.50027-7
book January 1977