Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Standard

Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma. / Li, Y.; Morgan, T.W.; van Dommelen, J.A.W.; Antusch, Steffen; Rieth, Michael; Hoefnagels, J.P.M.; Terentyev, Dmitry; De Temmerman, Gregory; Verbeken, Kim; Geers, M.G.D.

Nuclear Fusion. Vol. 60/4 2020. ed. Vienna : IAEA - International Atomic Energy Agency, 2020. p. 1-34 (Nuclear Fusion).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Li, Y, Morgan, TW, van Dommelen, JAW, Antusch, S, Rieth, M, Hoefnagels, JPM, Terentyev, D, De Temmerman, G, Verbeken, K & Geers, MGD 2020, Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma. in Nuclear Fusion. 2020 edn, vol. 60/4, Nuclear Fusion, IAEA - International Atomic Energy Agency, Vienna, pp. 1-34. https://doi.org/10.1088/1741-4326/ab77e7

APA

Li, Y., Morgan, T. W., van Dommelen, J. A. W., Antusch, S., Rieth, M., Hoefnagels, J. P. M., ... Geers, M. G. D. (2020). Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma. In Nuclear Fusion (2020 ed., Vol. 60/4, pp. 1-34). (Nuclear Fusion). Vienna: IAEA - International Atomic Energy Agency. https://doi.org/10.1088/1741-4326/ab77e7

Vancouver

Li Y, Morgan TW, van Dommelen JAW, Antusch S, Rieth M, Hoefnagels JPM et al. Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma. In Nuclear Fusion. 2020 ed. Vol. 60/4. Vienna: IAEA - International Atomic Energy Agency. 2020. p. 1-34. (Nuclear Fusion). https://doi.org/10.1088/1741-4326/ab77e7

Author

Li, Y. ; Morgan, T.W. ; van Dommelen, J.A.W. ; Antusch, Steffen ; Rieth, Michael ; Hoefnagels, J.P.M. ; Terentyev, Dmitry ; De Temmerman, Gregory ; Verbeken, Kim ; Geers, M.G.D. / Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma. Nuclear Fusion. Vol. 60/4 2020. ed. Vienna : IAEA - International Atomic Energy Agency, 2020. pp. 1-34 (Nuclear Fusion).

Bibtex - Download

@inproceedings{60145b0e25bd4ec9907b145c4dfaee65,
title = "Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma",
abstract = "The fracture behavior of plasma-facing components (PFCs) under extreme plasma-material interaction conditions is of great concern to ITER and future fusion reactors. This was explored in the current study by exposing pure tungsten (W), W-1{\%}TiC and W-2{\%}Y2O3 composites to a combined steady-state/transient hydrogen plasma up to a base surface temperature of ~ 2220 K, and up to 5000 transient pulses for 1000 seconds using the linear plasma generator Magnum-PSI. The applied heat loads were characterized by combining sheath physics, thermographic information and finite element analyses, with which the thermal stress was evaluated. Combining microstructural investigation and thermo-mechanical numerical analyses, a physical picture of fracture is developed. The transient heat loads drive surface crack initiation, whose depth can be estimated by a simple analytical model for pure tungsten, while the cooling period following the steady-state heat load induces tensile stresses, opening existing surface cracks deeper. The fracture process is mediated by the microstructure whereby the ceramic particles stabilize the microstructure but promote surface crack initiation due to suppressed plasticity at the grain boundaries and the particle-matrix interfaces. The surface cracks relieve the subsequent cycles of transient thermal stress but intensify the steady-state thermal stress, therefore, promoting deep crack propagation. These results help to understand failure mechanisms in PFCs under extreme operation conditions which are valuable for developing advanced PFCs.",
keywords = "Tungsten, ITER, Tungsten alloys, Pure W, Hydrogen, Fracture",
author = "Y. Li and T.W. Morgan and {van Dommelen}, J.A.W. and Steffen Antusch and Michael Rieth and J.P.M. Hoefnagels and Dmitry Terentyev and {De Temmerman}, Gregory and Kim Verbeken and M.G.D. Geers",
note = "Score=3",
year = "2020",
month = "3",
day = "16",
doi = "10.1088/1741-4326/ab77e7",
language = "English",
volume = "60/4",
series = "Nuclear Fusion",
publisher = "IAEA - International Atomic Energy Agency",
pages = "1--34",
booktitle = "Nuclear Fusion",
edition = "2020",

}

RIS - Download

TY - GEN

T1 - Fracture behavior of tungsten-based composites exposed to steadystate/ transient hydrogen plasma

AU - Li, Y.

AU - Morgan, T.W.

AU - van Dommelen, J.A.W.

AU - Antusch, Steffen

AU - Rieth, Michael

AU - Hoefnagels, J.P.M.

AU - Terentyev, Dmitry

AU - De Temmerman, Gregory

AU - Verbeken, Kim

AU - Geers, M.G.D.

N1 - Score=3

PY - 2020/3/16

Y1 - 2020/3/16

N2 - The fracture behavior of plasma-facing components (PFCs) under extreme plasma-material interaction conditions is of great concern to ITER and future fusion reactors. This was explored in the current study by exposing pure tungsten (W), W-1%TiC and W-2%Y2O3 composites to a combined steady-state/transient hydrogen plasma up to a base surface temperature of ~ 2220 K, and up to 5000 transient pulses for 1000 seconds using the linear plasma generator Magnum-PSI. The applied heat loads were characterized by combining sheath physics, thermographic information and finite element analyses, with which the thermal stress was evaluated. Combining microstructural investigation and thermo-mechanical numerical analyses, a physical picture of fracture is developed. The transient heat loads drive surface crack initiation, whose depth can be estimated by a simple analytical model for pure tungsten, while the cooling period following the steady-state heat load induces tensile stresses, opening existing surface cracks deeper. The fracture process is mediated by the microstructure whereby the ceramic particles stabilize the microstructure but promote surface crack initiation due to suppressed plasticity at the grain boundaries and the particle-matrix interfaces. The surface cracks relieve the subsequent cycles of transient thermal stress but intensify the steady-state thermal stress, therefore, promoting deep crack propagation. These results help to understand failure mechanisms in PFCs under extreme operation conditions which are valuable for developing advanced PFCs.

AB - The fracture behavior of plasma-facing components (PFCs) under extreme plasma-material interaction conditions is of great concern to ITER and future fusion reactors. This was explored in the current study by exposing pure tungsten (W), W-1%TiC and W-2%Y2O3 composites to a combined steady-state/transient hydrogen plasma up to a base surface temperature of ~ 2220 K, and up to 5000 transient pulses for 1000 seconds using the linear plasma generator Magnum-PSI. The applied heat loads were characterized by combining sheath physics, thermographic information and finite element analyses, with which the thermal stress was evaluated. Combining microstructural investigation and thermo-mechanical numerical analyses, a physical picture of fracture is developed. The transient heat loads drive surface crack initiation, whose depth can be estimated by a simple analytical model for pure tungsten, while the cooling period following the steady-state heat load induces tensile stresses, opening existing surface cracks deeper. The fracture process is mediated by the microstructure whereby the ceramic particles stabilize the microstructure but promote surface crack initiation due to suppressed plasticity at the grain boundaries and the particle-matrix interfaces. The surface cracks relieve the subsequent cycles of transient thermal stress but intensify the steady-state thermal stress, therefore, promoting deep crack propagation. These results help to understand failure mechanisms in PFCs under extreme operation conditions which are valuable for developing advanced PFCs.

KW - Tungsten

KW - ITER

KW - Tungsten alloys

KW - Pure W

KW - Hydrogen

KW - Fracture

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/38225696

U2 - 10.1088/1741-4326/ab77e7

DO - 10.1088/1741-4326/ab77e7

M3 - In-proceedings paper

VL - 60/4

T3 - Nuclear Fusion

SP - 1

EP - 34

BT - Nuclear Fusion

PB - IAEA - International Atomic Energy Agency

CY - Vienna

ER -

ID: 6785402