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The investigation of the carbon on irradiation hardening and defect clustering in RPV model alloy using ion irradiation and OKMC simulation

Li Jianyang|Zhang Chonghong|Yang Yitao
한국원자력학회 (Korean Nuclear Society)|2024.06|Nuclear Engineering and Technology|제56권 제6호|pp. 2071-2078|DOI 10.1016/j.net.2024.01.015

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CarbonReactor pressure vesselIrradiation hardeningOKMC simulation
주제분류원자력공학

초록

The precipitation of solutes is a major cause of irradiation hardening and embrittlement limiting the service life of reactor pressure vessel (RPV) steels. Impurities play a significant role in the formation of precipitation in RPV materials. In this study, the effects of carbon on cluster formation and irradiation hardening were investigated in an RPV alloy Fe-1.35Mn-0.75Ni using C and Fe ions irradiation at 290 ◦C. Nanoindentation results showed that C ion irradiation led to less hardening below 1.0 dpa, with hardening continuing to increase gradually at higher doses, while it was saturated under Fe ion irradiation. Atom probe tomography revealed a broad size distribution of Ni–Mn clusters under Fe ion irradiation, contrasting a narrower size distribution of small Ni–Mn clusters under C ion irradiation. Further analysis indicated the influence of carbon on the cluster formation, with soluteprecipitated defects dominating under C ion irradiation but interstitial clusters dominating under Fe ion irradiation. Simulations suggested that carbon significantly affected solute nucleation, with defect clusters displaying smaller size and higher density as carbon concentration increased. The higher hardening at doses above 1.0 dpa was attributed to a substantial increase in the number density of defect clusters when carbon was present in the matrix.

Abstract

The precipitation of solutes is a major cause of irradiation hardening and embrittlement limiting the service life of reactor pressure vessel (RPV) steels. Impurities play a significant role in the formation of precipitation in RPV materials. In this study, the effects of carbon on cluster formation and irradiation hardening were investigated in an RPV alloy Fe-1.35Mn-0.75Ni using C and Fe ions irradiation at 290 ◦C. Nanoindentation results showed that C ion irradiation led to less hardening below 1.0 dpa, with hardening continuing to increase gradually at higher doses, while it was saturated under Fe ion irradiation. Atom probe tomography revealed a broad size distribution of Ni–Mn clusters under Fe ion irradiation, contrasting a narrower size distribution of small Ni–Mn clusters under C ion irradiation. Further analysis indicated the influence of carbon on the cluster formation, with soluteprecipitated defects dominating under C ion irradiation but interstitial clusters dominating under Fe ion irradiation. Simulations suggested that carbon significantly affected solute nucleation, with defect clusters displaying smaller size and higher density as carbon concentration increased. The higher hardening at doses above 1.0 dpa was attributed to a substantial increase in the number density of defect clusters when carbon was present in the matrix.

참고문헌 (44)

  1. S. J. Zinkle, "Structural materials for fission & fusion energy", Mater. Today, 12, pp.12~19 (2009)
  2. W. -Y. Chen, "Neutron irradiation effects in Fe and Fe-Cr at 300 ◦C", Acta Mater, 111, pp.407~416 (2016)
  3. G. R. Odette, "Embrittlement of nuclear reactor pressure vessels", JOM, 53, pp.18~22 (2001)
  4. G. E. Lucas, "An evolution of understanding of reactor pressure vessel steel embrittlement", J. Nucl. Mater, 407, pp.59~69 (2010)
  5. S. Shu, "Precipitation in Fe-Cu and Fe-Cu-Mn model alloys under irradiation : dose rate effects", Acta Mater, 157, pp.72~82 (2018)
  6. L. Debarberis, "Analysis of WWER-440 and PWR RPV welds surveillance data to compare irradiation damage evolution", J. Nucl. Mater, 350, pp.173~181 (2006)
  7. L. T. Belkacemi, "Striking effect of solute elements (Mn, Ni) on radiation-induced segregation", precipitation in iron-based model alloys, 2021, pp.548, 152807~
  8. X. Hu, "Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation", J. Nucl. Mater, 470, pp.278~289 (2016)
  9. Y. -W. You, "Interaction of carbon, nitrogen and oxygen with vacancies and solutes in tungsten", RSC Adv, 5, pp.23261~23270 (2015)
  10. V. Jansson, "OKMC simulations of Fe–C systems under irradiation : sensitivity studies", J. Nucl. Mater, 452, pp.118~124 (2014)
  11. C. Domain, "Ab initiostudy of foreign interstitial atom (C, N)interactions with intrinsic point defects inα-Fe", Phys. Rev. B, 69 (2004)
  12. C. C. Fu, "Effect of C on vacancy migration in α-iron", Solid State Phenom, 139, pp.157~164 (2008)
  13. Y. -Z. Niu, "Influence of carbon on the evolution of irradiation defects in tungsten", J. Nucl. Mater, 579, pp.154393~ (2023)
  14. G. S. Was, "Challenges to the use of ion irradiation for emulating reactor irradiation", J. Mater. Res, 30, pp.1158~1182 (2015)
  15. S. J. Zinkle, "Opportunities and limitations for ion beams in radiation effects studies : bridging critical gaps between charged particle and neutron irradiations", Scr. Mater, 143, pp.154~160 (2018)
  16. Y. Yang, "A correlation between micro-and nano-indentation on materials irradiated by high-energy heavy ions", J. Nucl. Mater, 498, pp.129~136 (2018)
  17. Y. Yang, "Nanoindentation on V–4Ti alloy irradiated by H and He ions", J. Nucl. Mater, 459, pp.1~4 (2015)
  18. C. H. Zhang, "Irradiation response of ODS ferritic steels to high-energy Ne ions at HIRFL", J. Nucl. Mater, 455, pp.61~67 (2014)
  19. H. Zhang, "Irradiation hardening of ODS ferritic steels under helium implantation and heavy-ion irradiation", J. Nucl. Mater, 455, pp.349~353 (2014)
  20. G. S. Was, "Emulation of reactor irradiation damage using ion beams", Scr. Mater, 88, pp.33~36 (2014)
  21. S. Shen, "Effects of carbon doping on irradiation resistance of Fe38Mn40Ni11Al4Cr7 high entropy alloys", J. Nucl. Mater, 540, pp.152380~ (2020)
  22. Z. Su, "The effect of interstitial carbon atoms on defect evolution in high entropy alloys under helium irradiation", Acta Mater, 233, pp.117955~ (2022)
  23. J. F. Ziegler, "The Stopping and Range of Ions in Solids" (1984), Pergamon
  24. M. Chiapetto, "Nanostructure evolution under irradiation in FeMnNi alloys : a"grey alloy"object kinetic Monte Carlo model", J. Nucl. Mater, 462, pp.91~99 (2015)
  25. J. Li, "An object kinetic Monte Carlo simulation for defect evolution of neutron-irradiated reactor pressure vessel steels : carbon sensitive study", Phys. Status Solidi B, 258, pp.2100149~ (2021)
  26. R. S. Averback, "Atomic displacement processes in irradiated metals", J. Nucl. Mater, 216, pp.49~62 (1994)
  27. A. P. Thompson, "Lammps - a flexible simulation tool for particle-based materials modeling at the atomic, meso, and continuum scales", Comput. Phys. Commun, 271, pp.108171~ (2022)
  28. J. Byggm¨astar, "Effects of the short-range repulsive potential on cascade damage in iron", J. Nucl. Mater, 508, pp.530~539 (2018)
  29. A. Stukowski, "Visualization and analysis of atomistic simulation data with OVITO–the open visualization tool, modell", Simul. Mater. Sci. Eng, 18, pp.015012~ (2009)
  30. K. Nordlund, "Improving atomic displacement and replacement calculations with physically realistic damage models", Nat. Commun., 9 (2018)
  31. O. V. Ogorodnikova, "Verification of the theory of primary radiation damage by comparison with experimental data", J. Nucl. Mater, 525, pp.22~31 (2019)
  32. N. Soneda, "Defect production, annealing kinetics and damage evolution in α-Fe: an atomic-scale computer simulation", Philos. Mag. A, 78, pp.995~1019 (1998)
  33. D. Terentyev, "Carbon–vacancy interaction controls lattice damage recovery in iron", Scr. Mater, 86, pp.9~12 (2014)
  34. P. Hosemann, "Issues to consider using nano indentation on shallow ion beam irradiated materials", J. Nucl. Mater, 425, pp.136~139 (2012)
  35. W. D. Nix, "Indentation size effects in crystalline materials : a law for strain gradient plasticity", J. Mech. Phys. Solid, 46, pp.411~425 (1998)
  36. R. Kasada, "A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques", Fusion Eng. Des, 86, pp.2658~2661 (2011)
  37. C. D. Hardie, "Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys", J. Nucl. Mater, 439, pp.33~40 (2013)
  38. H. Watanabe, "Effects of Mn addition on dislocation loop formation in A533B and model alloys", J. Nucl. Mater, 439, pp.268~275 (2013)
  39. P. Prak Tom, "Effect of solute elements (Ni, Mn) in Fe-based alloys on dislocation loop evolution under Fe2+ ion irradiation", J. Nucl. Mater, 559, pp.153489~ (2022)
  40. E. Meslin, "Irradiation-Induced solute clustering in a low Nickel FeMnNi ferritic alloy", Exp. Mech, 51, pp.1453~1458 (2011)
  41. J. D. Hunn, "Helium and hydrogen induced hardening in 316LN stainless steel", J. Nucl. Mater, 282, pp.131~136 (2000)
  42. C. -L. Chen, "Dual beam irradiation of nanostructured FeCrAl oxide dispersion strengthened steel", J. Nucl. Mater, 412, pp.350~358 (2011)
  43. A. C. Fischer-Cripps, "Nanoindentation" (2011), Springer
  44. L. Tan, "Formulating the strength factor α for improved predictability of radiation hardening", J. Nucl. Mater, 465, pp.724~730 (2015)

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