journal article·2021-07-29

Numerical study of the influence of tungsten recrystallization on the divertor component lifetime

A. Durif, M. Richou, G. Kermouche, J-.M. Bergheau

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Abstract

The thermonuclear fusion reaction between deuterium and tritium could become an alternative, sustainable and safe way to generate electricity in demand. Plasma facing components will ensure the mechanical integrity of the reactor internal walls and the heat extraction and must be compatible with the plasma operation to not compromise its exploitation. ITER and WEST (W -for tungsten- Environment in Steady-state Tokamak) components will be exposed to particles fluxes during transient loading up to $$20\,\hbox {MW/m}2$$ . To withstand such loading, components are actively cooled and are made with pure tungsten as material facing the plasma. Although this technology fulfills ITER’s requirements, cracks appear in tungsten block under cyclic high heat flux at $$20\,\hbox {MW/m}2$$ . Such cracks propagate from the exposed surface to the cooling pipe. Even if the appearance of this crack does not immediately affect the component heat exhaust capability, it could limit the reactor operation. In literature, numerical models were developed and tungsten recrystallization was discussed as playing a significant role on the component lifetime. To improve the numerical predictions, this paper deals with the development of a Finite Element model dedicated to the lifetime prediction of tungsten-based Plasma Facing Components when subjected to very high heat fluxes. Recrystallized tungsten is known to offer lesser resistance to thermal fatigue damage than as-received rolled or forged tungsten. The main novelty of this paper lies in the modelling of tungsten recrystallization that happens after a given number of pulses. This fully coupled model predicts recrystallization, the induced change in mechanical properties and the resulting progressive damage. This final model, named RXMAT, is implemented as a user subroutine in the finite elements code ANSYS. Fueled by the tungsten recrystallization kinetics and by up to date as-received rolled tungsten and recrystallized tungsten elastic-viscoplastic constitutive laws, RXMAT links the tungsten recrystallization fraction evolution to a mechanical stress and strain fields for the first time. This was never done for tungsten employed as armoured material in experimental fusion reactors. This approach paves the way to develop a multiphysics numerical tool able to take into account the entire tokamak environment constraints (neutron irradiation, chemical reactions, thermal loads, etc) to predict the lifetime of tungsten-based Plasma Facing components.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced materials and composites

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References (43)

Show source-provided references
1. Alfonso LA, Pantleon W, Juul JD, Luo G (2015) Thermal stability of warm-rolled tungsten. DTU Mech Eng
2. Avrami M (1941) Kinetics of phase change. I: general theory. II: transformation-time relations for random distribution of nuclei. III: granulation, phase change and microstructure. J Chem Phys 7:1103–1112 (1939); 8:212–224 (1940); 9:177–184 (1941)10.1063/1.1750631 ↗
3. Bahm W (2005) Nuclear fusion programme annual report of the assiociation Forschungszentrum Karlsruhe/euratom, January 2004–December 2004. Technical report. 31.00.00; LK 01; Wissenschaftliche Berichte, FZKA-7117 (May 2005) EUR-21526-EN
4. Bergheau J-M, Mottet G, Débordes O (1998) Intégration numérique de lois de comportement élastoviscoplastique endommageable et applications. Rev Eur Eléments Finis, Taylor & Francis, vol. 7, $$n\circ 6$$, pp. 681–70810.1080/12506559.1998.10511332 ↗
5. Bergheau J-M (2014) Thermomechanical industrial processes: modeling and numerical simulation (ISTE). Wiley, New York10.1002/9781118578759 ↗
6. Charles Y et al (2018) Adaptation of hydrogen transport models at polycrystal scale and application to the U-bend test. Procedia Struct Integr 13:896–90110.1016/j.prostr.2018.12.169 ↗
7. Ciucani UM et al (2019) Recovery and recrystallization kinetics of differently rolled thin tungsten plates in the temperature range from $$1325\circ $$C-$$1400\circ $$C. Nucl Mater Energy 20:10070110.1016/j.nme.2019.100701 ↗
8. Durif A et al (2019) Impact of tungsten recrystallization on ITER-like components for lifetime estimation. Fusion Eng Des 138:247–25310.1016/j.fusengdes.2018.11.003 ↗
9. Durif A et al (2019) Inverse identification of tungsten static recrystallization kinetics under high thermal flux. Fusion Eng Des 146(B):1759–176310.1016/j.fusengdes.2019.02.141 ↗
10. Ezato K et al (2015) Progress of ITER full tungsten divertor technology qualification in Japan. Fusion Eng Des 98–99:1281–128410.1016/j.fusengdes.2015.03.009 ↗
11. Farre J, et al (1997) Etude de la transition fragile-ductile du tungstène. J. Phys. IV France 07:C3-879–C3-88410.1051/jp4:19973148 ↗
12. Fernandes FM, Denis S, Simon A (1985) Mathematical model coupling phase transformation and temperature evolution during quench of steels. Mat Sci Technol 10:838–84410.1179/mst.1985.1.10.838 ↗
13. Gavila P et al (2011) High heat flux testing of mock-ups for a full tungsten ITER divertor. Fusion Eng Des 86(9–11):1652–165510.1016/j.fusengdes.2011.02.012 ↗
14. Grosman A et al (2013) The WEST programme: minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER. Fusion Eng Des 88:497–50010.1016/j.fusengdes.2013.02.039 ↗
15. Habainy J et al (2015) Fatigue behavior of rolled ANF forged tungsten at 25, 280 and $$480\circ $$C. J Nucl Mater 465:438–47710.1016/j.jnucmat.2015.06.032 ↗
16. Hirai T et al (2016) Use of tungsten material for the ITER divertor. Nucl Mater Energy 9:616–62210.1016/j.nme.2016.07.003 ↗
17. Hirai T, et al (2015) Status of technology RD for the ITER tungsten divertor monoblock. J Nucl Mater 463:1248–1251 (Plasma-Surface Interactions 21)10.1016/j.jnucmat.2014.12.027 ↗
18. Humphreys FJ, Hatherly M (2004) Recrystallization and related annealing phenomena, 2nd edn. Elsevier, New York
19. ITER (2009) Heat and nuclear load specifications. d2luldhv 2.3
20. ITER structural design criteria for in-vessel components (SDC-IC) Appendix A: Materials design limit data. g74ma, 8 01-05-28w0.2 (2013)
21. Johnson WA, Mehl RF (1939) Reaction kinetics in process of nucleation and growth. Trans AIME 135:416–458
22. Leblond J-B (1989) Mathematical modelling of transformation plasticity in steels II: coupling with strain hardening phenomena. Int J Plast 5(6):573–59110.1016/0749-6419(89)90002-8 ↗
23. Leblond J-B Devaux (1984) A new kinetic model for anisothermal metallurgical transformations in steel including effect of austenite grain size. Acta Metall 32(1:137–14610.1016/0001-6160(84)90211-6 ↗
24. Lemaitre J, Chaboche J (2004) Mécanique des matrériaux solides. Science de l’ingénieur, Dunod, Sciences SUP
25. Li M, You J-H (2015) Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m2. Fusion Eng Des 101:1–810.1016/j.fusengdes.2015.09.008 ↗
26. Minissale M et al (2020) A high power laser facility to conduct annealing tests at high temperature. Rev Sci Instrum 91:035102. https://doi.org/10.1063/1.513374110.1063/1.5133741 ↗
27. Nogami et al (2017) Delegation of tungsten monoblock divertor under cyclic high heat flux loading. Fusion Eng Des 0:49–6010.1016/j.fusengdes.2017.04.102 ↗
28. Oda T (2016) Thermodynamic model for grain boundary effects on hydrogen solubility, diffusivity and permeability in poly-crystalline tungsten. Fusion Eng Des 112:102–11610.1016/j.fusengdes.2016.08.001 ↗
29. Panayotis S et al (2017) Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties. Nucl Mater Energy 12:200–20410.1016/j.nme.2016.10.025 ↗
30. Panayotis S et al (2017) Fracture modes of ITER tungsten divertor monoblock under stationary thermal loads. Fusion Eng Des 125:256–26210.1016/j.fusengdes.2017.08.009 ↗
31. Pintsuk G et al (2013) Qualification and post-mortem chracterization of tungsten mock-ups exposed to cyclic high heat flux loading. Fusion Eng Des 88:1858–186110.1016/j.fusengdes.2013.05.091 ↗
32. Pintsuk G et al (2015) Characterization of ITER tungsten qualification mock-ups exposed to high cyclic thermal loads. Fusion Eng Des 9899:13841388
33. Pumphey WI et al (1948) Inter-relation of hardenability and isothermal transformation data. JISI 159:137–144
34. Reiser J, et al (2013) Tungsten foil laminate for structural divertor applications—tenseile tests properties of tungsten foil. J Nucl Mater 434(1):357–366 (Special Section on Spent Nuclear Fuel)10.1016/j.jnucmat.2012.12.003 ↗
35. Riccardi B et al (2011) Preliminary results of the experimental study of PFCs exposure to ELMs-like transient loads followed by high heat flux thermal fatigue. Fusion Eng Des 86(9–11):1665–166810.1016/j.fusengdes.2011.04.069 ↗
36. Richou M et al (2020) Recrystallization at high temperature of two tungsten materials complying with the ITER specifications. J Nucl Mater 542:10.1016/j.jnucmat.2020.152418 ↗
37. Saint-Anthonin F (1997) Essais de relaxation isotherme. Techniques de l’ingénieur Essais mécaniques sur les métaux et alliages, base documentaire: TIB387DUO10.51257/a-v1-m141 ↗
38. Schmunk RE, Korth GE (1981) Tensile and low cycle fatigue measurements on cross-rolled tungsten. J Nucl Mater 103–104:943–94810.1016/0022-3115(82)90721-8 ↗
39. Schmunk RE, Korth GE, Ulrickson ML (1984) Tensile and low-cycle fatigue measurements on cross-rolled tungsten at 1505 K. J Nucl Mater 122–123:850–85410.1016/0022-3115(84)90711-6 ↗
40. Serret D et al, Thermal and Mechanical Characterizations of Warmoured Plasma Facing Components after Thermal Fatigue (Poster) 13th PFMC Conference, Rosenheim, 09–13 May 2011, Germany
41. Shah V et al (2021) Recrystallization behaviour of high-flux hydrogen plasma exposed tungsten. J Nucl Mater 545:10.1016/j.jnucmat.2020.152748 ↗
42. Visca E et al (2018) Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Eng Des 136:1593–159610.1016/j.fusengdes.2018.05.064 ↗
43. Wang K et al (2021) Recrystallization behavior of pure tungsten hot-rolled with high accumulated strain during annealing at $$1250\circ $$C - $$1350\circ $$C. Mater Sci Eng A 806:10.1016/j.msea.2021.140828 ↗