18 th International Conference on Plasma Surface Interaction in Controlled Fusion Toledo, Spain, May 26 – 30, 2008 1 Deuterium trapping in tungsten damaged.

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18 th International Conference on Plasma Surface Interaction in Controlled Fusion Toledo, Spain, May 26 – 30, Deuterium trapping in tungsten damaged by high- energy hydrogen ion irradiation M. Fukumoto, H. Kashiwagi, Y. Ohtsuka, Y. Ueda Graduate School of Engineering, Osaka University M. Taniguchi, T. Inoue, K. Sakamoto, J. Yagyu, T. Arai Japan Atomic Energy Agency I. Takagi Graduate School of Engineering, Kyoto University T. Kawamura, N. Yoshida Interdisciplinary Graduate School of Engineering Sciences, Kyushu University

2 Outline of this talk Background and Purpose of this study Experimental sequence Experimental results  D concentration in damaged W  Effects of annealing on D retention  TDS profiles as a function of incident fluence  Preliminary TMAP7 simulation Conclusion

3 Background and Purpose of this study Background of this study  In ITER, W is a candidate PFM for diverter region Extensive studies have been made for “undamaged” W  In DT fusion phase, fast neutrons are generated W is simultaneously irradiated by hydrogen isotopes and neutrons Interaction between radiation-induced defects and hydrogen isotope in W materials is very important  Trapping, release, and diffusion in damaged W are not clear Purpose of this study  Investigation of deuterium behavior in damaged W D depth distribution and desorption characteristics

4 Experimental sequence 1.Damage Creation  Ion energy: 300 keV H -  Pulse duration: 1 s every 60 s (~1000 shots)  Temperature: below 473 K (to avoid recovery of defects) 2.D implantation  Ion energy: 1.0 keV (D +, D 2 +, and D 3 + were contained)  Fluence: 0.5 x ~ 8.0 x D + /m 2  Temperature: 473 K 3.SIMS/NRA measurements  NRA was used for absolute calibration 4.TDS measurements  1 K/s, R.T. ~ 1100 K W samples  Hot rolled and stress relived  Mirror-polished less than 0.01  m roughness

5 D distribution as a function of fluence D conc. near surface was saturated at ~5.0x10 23 D + /m 2  D conc.: ~0.9x10 27 D/m 3  Trap density traps/W  Production rate traps/W·dpa  Similar to 800 MeV p damage* ~0.01 traps/W·dpa D conc. at ~1.0 µm was not saturated up to 8.0x10 24 D + /m 2 * B.M. Oliver et al., J. Nucl. Mater (2002) Fluence: 0.5 ~ 8.0 x D + /m 2 Temp.: 473 K Damage: ~4.8 dpa

6 Effects of 673 K annealing on D trapping D concentration was decreased by annealing at 673 K for 1 h.  Change of surface density 0.8x10 27 => 0.6x10 27 D/m 2  ~20 % reduction Most of self-interstitials could be eliminated*.  Vacancy type defects are still remained. * M. J. Attard et al., Phys. Rev. Lett., 19, (1967) 73. Fluence: 5.0 x D + /m 2 Temp.: 473 K Damage: ~4.9 dpa

7 Effects of 1173 K annealing on D trapping D conc. was also decreased by annealing at 1173K for 1h.  Change of surface density 0.9x10 27 => 0.2x10 27 D + /m 2  ~80 % reduction (near surface) Single vacancies could be annealed by this heat treatment*  Voids formation could be still take place** * D. Jeannotte et al., Phys. Rev. Lett., 19, (1967) 232. ** H. Eleveld et al., J.N.M., , (1994) Fluence: 5.0 x D + /m 2 Temp.: 473 K Damage: ~4.4 dpa

8 TDS spectra of two samples Fitted by Gaussian functions.  Peak 1: ~770 K  Peak 2: ~860 K  Peak 3: ~920 K Fluence: 5.0 x D + /m 2 Temp.: 473 K Undamaged W~4.8 dpa damaged W Damaged W has much higher D desorption

9 Fluence dependence of each peak Damaged samples  Peak 1 (~770 K) one order of magnitude higher than undamaged sample increased with fluence  Peak 2 (~860 K) same as undamaged sample constant with fluence  Peak 3 (~920 K) only damaged samples increased with fluence D was trapped at the defects related to Peak 1 (~770 K) and Peak 3 (~920 K) Fluence: 0.5 ~ 8.0 x D + /m 2 Temp.: 473 K Damage: ~4.8 dpa

10 D distribution simulated by TMAP7 Simulation conditions  Trap energy:1.34eV(vacancies)* 2.1eV (voids)*  Diffusion coeff.: Fraunfelder’s  Trapping rate:  De-trapping rate:  Distribution: TRIM-88  Trap density: traps/W·dpa  Other conditions: same as exp. D trapping proceeds from surface trapping sites All trap sites were filled less than 6.0 x D + /m 2  Much lower than exp. results (8.0 x D + /m 2 )  TMAP7 results did not agree with exp. results *M. Poon et al., JNM, 374 (2008) 390. D Concentration (x10 27 D/m 3 )

11 Conclusion Deuterium depth profiles  D conc. near surface was saturated at 5.0x10 23 D + /m 2 Damage production rate was similar to 800 MeV p irradiated W  D conc. at ~1.0  m was increased but not saturated up to 8.0x10 24 D + /m 2  Preliminary TMAP7 simulation did not reproduce exp. results Effect of annealing  Annealing at 673 K for 1 h decreased D retention by ~20 %  Annealing at 1173 K for 1 h decreased D retention by ~80 % TDS measurements  D was trapped at the radiation induced defects associated with Peak 1 (~770 K) and Peak 3 (~920 K)