PISCES W fuzz experiments: A summary of work up to now.

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1 FNST/PFC/MASCO meeting, UCLA Aug. 2-6, 2010 W fuzz experiments: A summary of work up to now. M.J. Baldwin, R.P. Doerner, D. Nishijima University of California, San Diego, USA

2 Why do we care about fuzz? W is an excellent FW material. Low sputter yield in detached plasma. High melt point (3695 K). Low D/T inventory >700 K. ITER divertor liner/dome are to be fabricated from W. T Wsurf < 1000 K. In the DT phase, ITER divertor will be all W metal. T Wsurf > 1000 K. But.... PMI research indicates that energetic He in contact w/ hot W will cause W fuzz., Baldwin et al. NF 48 (2008) NAGDIS II, Takamura, et al. Plasma and Fusion Res. 51 (2006) LHD, Tokitani et. al. JNM (2005) LP RF devices, Baldwin et al PSI San Diego P1 1 GLADIS device IPP Garching, H Greuner (2009) personal comm. IEC device walls Univ. of Wisconsin, Zenobia, JNM 389 (2009) PILOT PSI, G. Wright, G detemmerman, (2009) personal comm.

3 What causes fuzz? In W, He will bind readily with: 5.47 ev 4.15 ev 0.24 ev Vacancies (4.15 ev) Abd El Keriem et al. PR B 47 (1993) Impurities (1 3 ev). Kornelsen et al. JNM 92 (1980) 79 He i V. Abd El Keriem et al. PR B 47 (1993) Interstititial He (~1 ev). Becquart et al. PRL 97 (2006) (supported by calculation) W. Schilling, in Point Defects and Defect Interactions in Metals, Eds J.Takamura, M. Doyama, and M. Kiritani (North Holland, Amsterdam, 1982), p. 303.

4 What causes fuzz? ~ K ~ K > 2000 K (a) Bright field image (under focused image) B: pure He plasma M.J. Baldwin et al, NF 48 3 (2008) K, 4290 s, 2x10 26 He + /m 2, 25 ev He + 10nm A: He plasma M. Miyamoto et al. NF (2009) (in press) 600 K, 1000 s, 2.0x10 24 He + /m 2, 55 ev He + Little morphology Occasional blisters NAGDIS II: pure He plasma N. Ohno et al., in IAEA TM, Vienna, K, s, 3.5x10 27 He + /m 2, 11 ev He nm (VPS W on C) (TEM) Surface morphology Evolving surface Nano scale fuzz NAGDIS II: He plasma D. Nishijima et al. JNM (2004) Surface morphology Shallow depth Micro scale

5 Are any W or W alloy grades resilient to fuzz? Not yet., Baldwin et al. JNM (2010) in press

6 Can it get worse? Possibly., Baldwin et al. JNM (2010) in press

7 What does fuzz do the W surface? 2000 s, 1120 K 60 ev He + B pure He plasma 9000 s, 1120 K 60 ev He + B pure He plasma s, 1120 K 60 ev He + B pure He plasma ~4 ITER shots RN ~20 ITER shots Comparable to RN ~50 ITER shots RN

8 Growth rate of Fuzz? t 1/2 Δ=βt 1/2, where β = m 2 s 1 at 1120 K. Alarming re growth rate, dδ/dt = β/(2t 1/2 ). Ablation, ELMS, etc causing reduced layer thickness δ, lead to re growth rate: (dδ/dt) Δ= δ = β 2 /(2δ) depending on whether equilibrium can be maintained. Experiment to test this using pulsed laser heat loads underway. Layer thickness, Δ (μm) 0 5 T s =1320 K He T s =1120 K He t (s) T s =1120 K -0.2He

9 Does D affect fuzz, since He is a reactor minority species? No Fuzz layer growth after 3600 s in He and pure He plasmas shows a trend. Layer growth rate increases exponentially for Γ He+ up to ~ m 2 s 1. Layer growth rate is optimal above this.c Layer thickness (μm) ITER (Outer strike plate) A. Kukushkin, ITER Report, [ITER_D_27TKC6] He -He t = 3600 s T s = 1120 K Γ He + (m -2 s -1 )

10 How does fuzz erode? W/ lower Y. Fuzz produced on W by He plasma exposure over 800 s at 1150 K, E i ~ 90 ev. Switch to He/Ar plasma at t = 0 s, & measure time evolution of W I emission in front of W target. Y smooth (Ar + W) E i ~ 110 ev, by mass loss. (Agrees w/ TRIM). Y fuzzy = (0.05 / WI/ArII 110 ev, smooth) x WI/ArII Why is the sputtering yield reduced? Porosity? Internal bubble? Not well understood.

11 Is there a growth/erosion equilibrium. Yes 250 ev He μm 10 W 1120K W fuzz growth Y PA = 3.4e-4 (250 ev) Y PA = 1.5e-4 (200 ev) Fuzz layers after 3600 s in He plasma at 1120 K 2.0 μm x Expected fuzz thickness in one hour with no erosion (60 ev He + ) x x 200 ev He + 60 ev He μm W fuzz layer thickness (nm) Growth rate Baldwin et al., NF 48(2008) W fuzz yield Nishijima et al., PSI 19 Exploring application of method to ITER W divertor conditions

12 Fuzz and gaps? LOS or NLOS? SEM section fuzz bulk (on surface) Benchmark gap target produced in PA. Currently collaborating with D Boridin of Forschungszentrum Jülich to model observations. 11 mm 25 mm -A He plasma on W (0.5, 1.0, 1.5 mm) gap target T s = 1100 K T exp = 3600 s E ion ~ 70 ev Γ He+ = cm -2 s mm 1.0 mm 1.5 mm (non LOS) FUZZ (in gaps)

13 D Retention in fuzz? Very low! DEUTERIUM HELIUM Temperature (K) Temperature (K) Little or no D is detected during TDS when He is used as a pretreatment or admixture to/in D plasma. D inventory below detection limit (~10 18 D/m 2 ) in cases where fuzz was exposed to D or D:He plasma. Fuzz seems to be a remarkable permeation barrier. m/e = 4 partial pressure (x10-9 Torr) -9 Torr) m/e = 4 partial pressure (x10-9 Torr) -9 Torr) on W 'fuzz' [-.- x10 -- D /m 2 ] -He(10%) on W [1.1 x10 20 D /m 2 ] on W [5.0 x10 20 D /m 2 ] m/e = 4 partial pressure (x10-9 Torr) Time (s) Time (s) Fluence[D + ] ~5 x10 25 m -2, T s ~420 K, E i ~30 ev DEUTERIUM HELIUM Temperature (K) Temperature (K) only [no fuzz] -He(10%) [fuzz] He only [fuzz] m/e = 4 partial pressure (x10-9 Torr) He interstitial? on W w/ 'fuzz' layer -He(10%) on W on W only [no fuzz] -He(10%) [fuzz] He only [fuzz] He V He - V binding (bubble precursers) He n>10 -V Time (s) Fluence ~2 x10 26 m -2, T s ~1120 K, E i ~50 ev Time (s)

14 How does fuzz take power loads? Initial tests encouraging. Selected W samples exposed to the Magnetized Co axial Plasma Gun (MCPG) at Univ. of Hyogo, Japan. Energy density: ~ MJ/m 2 Pulse width: ~0.5 ms Ion energy for D + : ~30 ev n e ~10 21 m 3, Γ i ~ 1 2x10 25 m 2 s 1 Comparable to type I ELMs in ITER

15 Summary of fuzz PMI experiments. Pros Cons What Next? Self limited t 1/2 growth at surface. Erodes with low sputter yield w.r.t bulk W. Very low hydrogen isotope retention. Good permeation barrier. Seemingly resilient to power loads. Fuzz will manifest in long pulse high T reactors w/ FW W. Unknown surface properties w.r.t W. Potential for enhanced material loss during transients. Surface and potential deep GB destruction. Found in gaps. HIGH Z dust? Materials modeling to understand growth mechanisms. Resilience/erosion under continuous transient loads Develop mitigation strategies (T control, heavy alloying etc??) Can we live with fuzz: Do the Pros outweigh Cons?

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