journal article·2023-07

Laser repair of tungsten damaged by fusion-relevant plasmas

Yu Li, Chuan Guo, Yuhan Sun, Long Cheng, JiaGuan Peng, Yue Yuan, Guang-Hong Lu, Qiang Zhu

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Abstract

As a hotspot, the ITER tungsten divertor receives both extreme plasmas and considerable research attention. The projection is that certain plasma-induced defects in tungsten are inevitable under the scheduled ITER operation. Although the exact consequences of such defects on the divertor lifetime are unclear currently, approaches to combat them are desirable but remain limited. Here, we develop the idea of healing such defects through laser remelting. With a suitable combination of processing parameters—such as laser power, scan speed, and preheating temperature—the remelted (pristine) tungsten surface was nearly crack-free. Revealed by electron backscatter diffraction (EBSD) analysis, the remelted microstructure resembled that of fully recrystallized tungsten. Furthermore, the linear relationship between the normalized melt pool depth and the normalized enthalpy of the surface was established, the former of which indicates the healing depth. Lastly, proof-of-principle experiments were performed on damaged tungsten specimens containing respectively blisters, nanostructure fuzz, and fatigue cracks, yielding promising healing effects. Based on additional considerations of the plasma exposure behavior of laser remelted tungsten and deployment of the laser repair system, we conclude that the laser repair approach is compatible with the ITER operation plan.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis

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References (40)

Show source-provided references
1. Physics basis for the first ITER tungsten divertor
2. Blister formation on tungsten surface under low energy and high flux hydrogen plasma irradiation in NAGDIS-I10.1016/S0022-3115(02)01349-1 ↗
3. Subsurface morphology changes due to deuterium bombardment of tungsten10.1088/0031-8949/2009/T138/014040 ↗
4. Formation of helium induced nanostructure ‘fuzz’ on various tungsten grades10.1016/j.jnucmat.2010.06.034 ↗
5. Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions10.1088/0029-5515/49/9/095005 ↗
6. Transient heat load challenges for plasma-facing materials during long-term operation10.1016/j.nme.2016.12.024 ↗
7. Combined high fluence and high cycle number transient loading of ITER-like monoblocks in Magnum-PSI10.1088/1741-4326/ac25c2 ↗
8. Effect of strike point displacements on the ITER tungsten divertor heat loads10.1088/1741-4326/aae43f ↗
9. Laser re-melting of tungsten damaged by transient heat loads10.1016/j.nme.2016.04.004 ↗
10. High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility10.1016/j.fusengdes.2019.04.020 ↗
11. Development and optimization of STEP—a linear plasma device for plasma-material interaction studies10.13182/FST16-115 ↗
12. Texture analysis with MTEX–free and open source software toolbox10.4028/www.scientific.net/SSP.160.63 ↗
13. A review of tungsten fabricated via laser powder bed fusion10.1007/s42864-021-00089-3 ↗
14. Single crystalline-like crystallographic texture formation of pure tungsten through laser powder bed fusion10.1016/j.scriptamat.2021.114252 ↗
15. Brittle–ductile transitions in polycrystalline tungsten10.1080/14786435.2010.502145 ↗
16. Analysis of laser-induced microcracking in tungsten under additive manufacturing conditions: experiment and simulation10.1016/j.actamat.2020.04.060 ↗
17. Fracture behavior of tungsten-based composites exposed to steady-state/transient hydrogen plasma10.1088/1741-4326/ab77e7 ↗
18. Additive manufacturing of pure tungsten by means of selective laser beam melting with substrate preheating temperatures up to 1000 ∘C10.1016/j.nme.2019.02.034 ↗
19. Microcrack mitigation during laser scanning of tungsten via preheating and alloying strategies
20. A simple methodology for predicting laser-weld properties from material and laser parameters10.1088/0022-3727/44/44/445401 ↗
21. Laser energy absorption coefficient and in-situ temperature measurement of laser-melted tungsten10.1016/j.fusengdes.2017.04.025 ↗
22. Analytical expressions for thermophysical properties of solid and liquid tungsten relevant for fusion applications10.1016/j.nme.2017.08.002 ↗
23. thermophysical properties of matter-The TPRC data series
24. Recrystallization-mediated crack initiation in tungsten under simultaneous high-flux hydrogen plasma loads and high-cycle transient heating10.1088/1741-4326/abe312 ↗
25. Influence of porosity and blistering on the thermal fatigue behavior of tungsten10.1088/1741-4326/ac6a65 ↗
26. A new hot-tearing criterion10.1007/s11661-999-0334-z ↗
27. Analysis of tungsten melt-layer motion and splashing under tokamak conditions at TEXTOR10.1088/0029-5515/51/8/083008 ↗
28. Numerical simulations of tungsten melt layer erosion caused by J×B force at TEXTOR
29. Melt-layer motion and droplet ejection under divertor-relevant plasma conditions10.1088/0029-5515/53/2/023008 ↗
30. Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading10.1016/j.fusengdes.2013.05.091 ↗
31. Status of technology R&D for the ITER tungsten divertor monoblock10.1016/j.jnucmat.2014.12.027 ↗
32. Influence of the microstructure on the deuterium retention in tungsten10.1016/j.jnucmat.2010.10.045 ↗
33. Effect of starting microstructure on helium plasma-materials interaction in tungsten10.1016/j.actamat.2016.11.042 ↗
34. Flux and fluence dependent helium plasma-materials interaction in hot-rolled and recrystallized tungsten10.1016/j.jnucmat.2018.07.048 ↗
35. Monitoring of tritium and impurities in the first wall of fusion devices using a LIBS based diagnostic10.1088/1741-4326/ac31d6 ↗
36. An empirical scaling for deuterium retention in co-deposited beryllium layers10.1088/0029-5515/48/7/075008 ↗
37. A reduced model for the ITER divertor based on SOLPS solutions for ITER Q = 10 baseline conditions. Part A: identifying options for the control parameters
38. The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets10.1088/1361-6587/aaaf62 ↗
39. High-flux hydrogen irradiation-induced cracking of tungsten reproduced by low-flux plasma exposure10.1088/1741-4326/ab0915 ↗
40. A review of late-stage tungsten fuzz growth10.1007/s42864-021-00133-2 ↗