1. Dynamic evolution of mixed materials bombarded with multiple ions beams and impurities Tatyana Sizyuk Ahmed Hassanein School of Nuclear Engineering Center for Materials Under eXtreme Environment Purdue University PFC community meeting at UCLA August 4-6, 2010, Los Angeles CA

2. 2 ITMC-DYN Computer Simulation Package Collision-induced reactions + Diffusion, Segregation, Chemical erosion, Surface recombination, and Desorption Benchmarking for ELM averaged regimes Benchmarking for TEXTOR discharges PWI and material issues for ITER performance Future code extension: (1) Chemical reaction rates + detailed processes of chemical erosion (2) 3D target structure for nonideal surface erosion Summary Outline

3. 3 ITMC-DYN Integrated Models A. Hassanein, “Surface effects on sputtered atoms and their angular and energy dependence”, Fusion Technology 8 (1985) 1735. A. Hassanein and D.L. Smith, “Elastic and inelastic surface effects on ion penetration and the resulting sputtering and backscattering”, Nuclear Instruments and Methods in Physics Research B13 (1986) 225. T. Sizyuk and A. Hassanein, "Dynamic analysis and evolution of mixed materials bombarded with multiple ions beams", J. Nucl. Mater., available online 1 July 2010 T. Sizyuk and A. Hassanein “Dynamic analysis of mixed ion beams/materials effects on the performance of ITER-like devices“, to be published J. Nucl. Mat. (2010)

4. 4 ITMC-DYN Integrated Modeling  Collision models are integrated with detail models of time-dependent processes such as atom diffusion and segregation. Therefore, we consider actual fluences and exact irradiation times of laboratory experiments.  Time step is determined from processes of diffusion, molecular recombination, and surface segregation.  Additional surface boundary conditions are used to specify the recombination of a diatomic hydrogen isotope molecules and their release from the surface in modeling of both laboratory and reactor conditions.  Surface segregation models are implemented and helped to explain recent experimental results.  Chemical erosion of carbon is calculated in each layer near the surface, depending on carbon concentration. Erosion yield is compared with that predicted by well-defined and benchmarked formula.

5. 5 Simulation Results of ITMC-DYN  Influence of binding energy on surface build-up and recession 2.0 eV binding energy of Cs 0 eV binding energy of Cs Effect of potential and fluence on surface growth/erosion of Cs (on Si surface) with 0 eV binding energy of Cs in modeling

6. 6 Testing Dynamic Update of Materials Composition  Nano-scale multilayers formation – 90 eV Fe + and 50 eV C + -> Si ITMC-Dyn – 4 bilayer periods: ~1.1 nm, ~ 1.8 nm, ~ 2 nm, ~ 4.3 nm. (each from 2 bilayers) High-resolution TEM micrograph of Fe/C multilayers with 4 bilayer periods: 0.75 nm, 1.25 nm, 2.5 nm and 5.0 nm in order from the Si substrate, respectively.

7. 7 Testing Dynamic Update of Materials Composition  Nano-scale multilayers formation – 90 eV Fe + and 50 eV C + -> Si ITMC-Dyn – 4 bilayer periods: ~1.1 nm, ~ 1.8 nm, ~ 2 nm, ~ 4.3 nm. (each from 2 bilayers) Sung-Yong Chun, “TEM-examination and computer simulation of nano- scale multilayers by pulsed cathodic arc deposition”, Journal of Ceramic Processing Research. Vol. 4, No. 3, pp. 115~117 (2003)

8. 8 Benchmarking Multiple Beams on Targets  Beams of hydrogen ions containing carbon impurity ions were impinged on pure tungsten samples heated from 653 to 1050 K.  Ion beams consisted of 70% of 333 eV H +, 10% of 500 eV H +, 20% of 1000 eV H + and from 0.1% to 1% of C ions with 1000 eV energy.  Carbon concentration on the surface of tungsten was measured and conditions for blisters formation were investigated in dependence on the total fluence, on % of carbon concentration in ion beams, and on samples temperatures. 1) Y. Ueda, T. Shimada, and M. Nishikawa, "Impacts of carbon impurities in hydrogen plasmas on tungsten blistering", Nucl. Fusion 44 (2004) 62 2) T. Shimada, T. Funabiki, R. Kawakami, Y. Ueda, M. Nishikawa, "Carbon behavior on tungsten surface after carbon and hydrogen mixed beam irradiation", J. Nucl. Mater., 329–333 (2004) 747– 751

9. 9 Blisters formation and dependence on target temperature  Blisters formation depends on mobility of implanted gas and on concentration of gas atoms in the target  Accumulation of H in tungsten target in the experiments can be due to lattice imperfections, ion-induced damage (that is not applicable for low energies of H ions), and carbon deposition  In these experiments carbon was deposited in the form of graphite or in binding with tungsten (WC or W 2 C) on the surface of the samples

10. 10 Modeling of Ions/Target Interactions (ITMC-DYN) Beam of H with C Impurities on W surface T. Shimada, T. Funabiki, R. Kawakami, Y. Ueda, M. Nishikawa, "Carbon behavior on tungsten surface after carbon and hydrogen mixed beam irradiation", J. Nucl. Mater., 329–333 (2004) 747–751 ITMC-Dyn modeling with diffusion coefficient of H in dependence on carbon concentration in W target and for temperature of target 653 K Fluence 3x10 24 /m 2 0.8 % of C

11. 11 Modeling of Ions/Target Interactions (ITMC-DYN) Beam of H with C Impurities on W surface ITMC-Dyn modeling with diffusion coefficient of H in dependence on carbon concentration in W target and for temperature of target 453 K It was reported in the experiment that at 453 K a high densities of blisters formed Fluence 3x10 24 /m 2 0.8 % of C

12. 12 Modeling of Ions/Target Interactions (ITMC-DYN) Beam of H with C Impurities on W surface ITMC-Dyn modeling with diffusion coefficient of H in dependence on carbon concentration in W target and for temperature of target 653 K It the experiment blisters appeared under this fluence and target temperature 653 K Fluence 3x10 23 /m 2 0.8 % of C

13. 13 Dependence of blisters formation on impurity concentrations The difference in the target erosion explains the difference in peak location. Carbon atoms, redistributed inside the W target by incoming hydrogen ions, are then removed by surface erosion and this process is accelerated in the case of 0.84% C concentration in beam. The lower content of carbon of 0.11% in comparison with 0.84% resulted in the following differences in samples:  Peak carbon concentration changed from 40% to more than 60%  its location is shifted 15-20 nm from the surface in the case of 0.11% and 7- 8 nm in the case of 0.84%  target erosion is almost 10 times higher under the ion fluence containing 0.84% C

14. 14 Modeling of Ions/Target Interactions (ITMC-DYN) Beam of H with C Impurities on W surface  Conclusion: Low level of impurity contents in plasma can significantly affect erosion lifetime, largely increase hydrogen isotope retention, and enhance bubble/blister formation in candidate reactor materials in fusion environments.  Evidence from other experiments: “It is assumed that tungsten carbide formed on the W surface under exposure to the carbon-seeded D plasmas serves as a barrier layer for diffusion and prevents the outward transport of deuterium, thus increasing the D retention in the bulk of tungsten.” V. Kh. Alimov, et al., “Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmas”, J. Nucl. Mater. 375 (2008) 192

15. 15 Effects of segregation and etching on carbon concentration in target  Surface segregation moves carbon atoms from bulk to surface layer because of increasing chemical potential of carbon in the bulk of W/C compound.  Implementing surface segregation can shift peak of carbon concentration profile closer to the surface  However simulating this processes self-consistently with ions beam deposition, target atoms sputtering, and atom cascade redistribution  have the effect that surface segregation loses its effectiveness

16. 16 Influence of Post Irradiation Processes – Surface Segregation, Diffusion and Etching  Post-ion-deposition surface segregation, and subsequent processes of etching of samples  Etching is done using 1.7 keV Ar ions in experiments for measurement of carbon concentration profile  This can explain the reason of the enhanced carbon accumulation on the surface

17. 17 Test of Diffusion Modeling Carbon deposition, knock-out by H and diffusion in W Self-consistently

18. 18 Influence of Post Irradiation Processes – Surface Segregation and Diffusion

19. 19 Influence of Post Irradiation Processes – Etching by 1.7 keV Ar ions

20. 20 Benchmarking TEXTOR discharges Textor limiter was exposed at a radial distance R = 48.5 cm from plasma center and 2.5 cm behind the last close flux surface (LCFS) during 125 plasma discharges with a total duration of 559 plasma seconds Edge plasma parameters during the experiment were measured with fast probe and He-beam diagnostics. The ion fluence on the limiter estimated using He-beam data had a value of 4.9 · 10 19 ion/cm 2 averaged over the area of castellation Surface temperature of the limiter was varied from 200 C to 400 C which agrees well with values expected for upper vertical targets of ITER divertor [A. Litnovsky, et al., J. Nucl. Mater. 367–370 (2007) 1481]

21. 21 Benchmarking TEXTOR discharges Parameters for modeling were used based on fast probe measurements: 120 eV D ions, 300 eV C ions Parameters for TEXTOR experiments: Ion flux - 2.5x10 17 D/sm 2 /s; 1%, 2% and 3% of C in the beam; 600 K temperature in W At carbon concentration in beam of 3%, carbon layer covers tungsten surface and can prevent hydrogen diffusion to the bulk

22. 22 Blistering at similar to TEXTOR conditions V. Kh. Alimov, et al., “Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmas”, J. Nucl. Mater. 375 (2008) 192 1x10 17 D/cm 2 /s flux ‘clean’ and carbon- seeded D plasmas (ion fluence of about 2x10 20 D/cm 2 );  200 eV/D Impurity concentration in the near surface layer:

23. 23 Integrated Modeling issues for PWI Erosion, re-deposition Mixed ions beams with impurities, erosion of compounds, coupling with above surface plasma codes D and T retention Hydrogen diffusion, molecular recombination and desorption, chemical erosion, saturation in C and Be, agglomeration and blistering in W He retention He diffusion, bubbles and blisters formation, W surface modification Surface morphology Physical sputtering and impurities deposition in dependence on surface conditions Mixing and alloying Chemical reactions rates for compounds formation V. Philipps, 19th PSI San Diego 2010

24. 24 Code extension: reaction rates for compounds formation at first wall materials Elementary reactions, equations for reaction fluxes and experimental reaction parameters (sample of Be and C compound): 2 Be + C → Be 2 C Be 2 C → 2 Be + C formation reaction fluxes destruction reaction fluxes Ch. Linsmeier, 19th PSI San Diego 2010 Solving rate equations: Be 2 C formation: ΔE=1.8 eV (exp.), k 0 = 10 -29 m 4 /s Be 2 C dissociation: ΔE=3.0 eV (from ΔH f ), k 0 = 10 13 s -1

25. 25 Code extension: detailed processes of chemical erosion Three processes determine the chemical erosion of carbon under low-energy hydrogen bombardment: Reaction of thermalized ions within implanted surface proceeds via the hydrogenation of carbon atoms at edges of graphitic planes to CH 3 –C complexes Thermal reaction is enhanced by radiation damage induced in material that provides open bonds for hydrogen attachment. At low surface temperatures: kinetic hydrocarbon emission or surface effects, since hydrocarbon radicals are bound to surface with much less binding energy (≈1 eV) than are carbon atoms in their regular lattice environment (7.4 eV) J. Roth, et al., Nucl. Fusion 44 (2004)

26. 26 Code extension: 3D target structure for exploring nonideal surface erosion For exploring of: Shin Kajita, 19th PSI San Diego 2010 Surface roughness effects on impurities deposition  This will be accomplished by significantly increasing mesh size and target structure with parallel implementation of code running at ANL Supercomputers Y. Ueda, J. Nucl. Mater. 390–391 (2009) Sputtering and deposition in W fuzz

27. 27 Summary & Conclusion  A new dynamic version of ITMC code is developed (ITMC-DYN)  This version is capable of dynamically simulating target composition changes and all physical processes as a function of irradiation time  New models and simulation of diffusion, segregation, chemical erosion, and etching processes are developed and implemented  Initial results of modeling were presented and compared quite well with recent laboratory experiments of mixed ion beams and the effect of blister formation in tungsten material  Future work ($$ ?) will include more detailed reaction processes and simulating more complicated experiments, real reactor conditions, and to propose/recommend laboratory experiments to enhance our understanding of mixed materials behavior and effects

28. 28 Thank You

29. 29 Examples of Simulation Results  Influence of binding energy on surface build-up and recession W. Eckstein et al.,”Ion-induced alkali-silicon interfaces: Atomistic simulations of collisional effects”, Nucl. Instr.Meth. B119 (1996) 477- 486 ITMC-DYN – Effect of potential and fluence on surface growth/erosion of Cs (on Si surface) with 0 eV binding energy of Cs in modeling

30. 30 Rates of mass losses Fluence 3x10 24 /m 2 ; target temperature – 653 K; C/H = 0.84%

31. 31 PWI and Material Issues for ITER Performance Erosion, re-deposition T retention He retention Surface morphology Cracking Melting and melt stability Mixing and alloying V. Philipps, 19th PSI San Diego 2010

32. 32 Code extension: detailed processes of chemical erosion Total methane erosion can be calculated as sum of temperature dependent erosion Y T (Mech model) And kinetic part Y 0 (Hopf model for temperature 300 K) We will implement also in model: Inventory of different hybridization states of carbon atoms (sp 2, sp 3 and sp 3 H ) Control of upper limit of H atoms bounded to C (1/3) Control of maximum sp 3 centers as function of temperature