Fracture-mechanical properties of neutron irradiated ITER specification tungsten

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Fracture-mechanical properties of neutron irradiated ITER specification tungsten. / Caganidze, A.; Chauhan, A.; Schneider, Hans-Christian; Terentyev, Dmitry; Borghmans, Gitte; Aktaa, Jarir.

In: Journal of Nuclear Materials, Vol. 547, 152761, 08.01.2021, p. 1-8.

Research output: Contribution to journalArticle

Harvard

Caganidze, A, Chauhan, A, Schneider, H-C, Terentyev, D, Borghmans, G & Aktaa, J 2021, 'Fracture-mechanical properties of neutron irradiated ITER specification tungsten', Journal of Nuclear Materials, vol. 547, 152761, pp. 1-8. https://doi.org/10.1016/j.jnucmat.2020.152761

APA

Caganidze, A., Chauhan, A., Schneider, H-C., Terentyev, D., Borghmans, G., & Aktaa, J. (2021). Fracture-mechanical properties of neutron irradiated ITER specification tungsten. Journal of Nuclear Materials, 547, 1-8. [152761]. https://doi.org/10.1016/j.jnucmat.2020.152761

Vancouver

Caganidze A, Chauhan A, Schneider H-C, Terentyev D, Borghmans G, Aktaa J. Fracture-mechanical properties of neutron irradiated ITER specification tungsten. Journal of Nuclear Materials. 2021 Jan 8;547:1-8. 152761. https://doi.org/10.1016/j.jnucmat.2020.152761

Author

Caganidze, A. ; Chauhan, A. ; Schneider, Hans-Christian ; Terentyev, Dmitry ; Borghmans, Gitte ; Aktaa, Jarir. / Fracture-mechanical properties of neutron irradiated ITER specification tungsten. In: Journal of Nuclear Materials. 2021 ; Vol. 547. pp. 1-8.

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@article{f525db399c254844b4af01a9726b7aae,
title = "Fracture-mechanical properties of neutron irradiated ITER specification tungsten",
abstract = "The work focuses on the investigation of the influence of neutron irradiation on the fracture mechani- cal properties of ITER specification-conform, stress-relieved tungsten bar. The irradiation of miniaturized Three-Point Bend specimens was performed inside the fuel channel of the Material Test High Flux BR2 reactor of SCK • CEN in Mol. An irradiation damage dose close to 1 dpa (in tungsten) was achieved at 800 °C with active temperature cooling and constant on-line temperature monitoring. Thick-wall stainless steel capsules were implemented for shielding the thermal neutrons in order to reduce Re transmuta- tion down to ~2 at.{\%} (and 0.2 at.{\%} Os). The quasi-static fracture mechanical experiments were carried out following ASTM E399 aiming at the determination of plane strain fracture toughness K Ic . The post irradiation examination of the specimens irradiated at 800 °C reveals severe material embrittlement. At T test = T irr = 800 °C, a deformation free brittle fracture is observed. The fractographic investigations show a mixture of brittle transgranular cleavage and intergranular fracture. With increasing the test tempera- ture above 10 0 0 °C, the fracture mode is changed from the brittle to a ductile one. Blunting of the notch tip leads to a suppression of the crack initiation and propagation and consequently no failure of the spec- imens was observed up to severe deflection levels. In some cases, however, a ductile crack growth with a characteristic dimple formation was identified, in addition. Based on the obtained results, the Ductile to Brittle Transition Temperature shift induced by the neutron irradiation at 800 °C is evaluated to be 600-625 °C.",
keywords = "Polycrystalline tungsten, Fracture behaviour, Neutron irradiation",
author = "A. Caganidze and A. Chauhan and Hans-Christian Schneider and Dmitry Terentyev and Gitte Borghmans and Jarir Aktaa",
note = "Score=10",
year = "2021",
month = "1",
day = "8",
doi = "10.1016/j.jnucmat.2020.152761",
language = "English",
volume = "547",
pages = "1--8",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Fracture-mechanical properties of neutron irradiated ITER specification tungsten

AU - Caganidze, A.

AU - Chauhan, A.

AU - Schneider, Hans-Christian

AU - Terentyev, Dmitry

AU - Borghmans, Gitte

AU - Aktaa, Jarir

N1 - Score=10

PY - 2021/1/8

Y1 - 2021/1/8

N2 - The work focuses on the investigation of the influence of neutron irradiation on the fracture mechani- cal properties of ITER specification-conform, stress-relieved tungsten bar. The irradiation of miniaturized Three-Point Bend specimens was performed inside the fuel channel of the Material Test High Flux BR2 reactor of SCK • CEN in Mol. An irradiation damage dose close to 1 dpa (in tungsten) was achieved at 800 °C with active temperature cooling and constant on-line temperature monitoring. Thick-wall stainless steel capsules were implemented for shielding the thermal neutrons in order to reduce Re transmuta- tion down to ~2 at.% (and 0.2 at.% Os). The quasi-static fracture mechanical experiments were carried out following ASTM E399 aiming at the determination of plane strain fracture toughness K Ic . The post irradiation examination of the specimens irradiated at 800 °C reveals severe material embrittlement. At T test = T irr = 800 °C, a deformation free brittle fracture is observed. The fractographic investigations show a mixture of brittle transgranular cleavage and intergranular fracture. With increasing the test tempera- ture above 10 0 0 °C, the fracture mode is changed from the brittle to a ductile one. Blunting of the notch tip leads to a suppression of the crack initiation and propagation and consequently no failure of the spec- imens was observed up to severe deflection levels. In some cases, however, a ductile crack growth with a characteristic dimple formation was identified, in addition. Based on the obtained results, the Ductile to Brittle Transition Temperature shift induced by the neutron irradiation at 800 °C is evaluated to be 600-625 °C.

AB - The work focuses on the investigation of the influence of neutron irradiation on the fracture mechani- cal properties of ITER specification-conform, stress-relieved tungsten bar. The irradiation of miniaturized Three-Point Bend specimens was performed inside the fuel channel of the Material Test High Flux BR2 reactor of SCK • CEN in Mol. An irradiation damage dose close to 1 dpa (in tungsten) was achieved at 800 °C with active temperature cooling and constant on-line temperature monitoring. Thick-wall stainless steel capsules were implemented for shielding the thermal neutrons in order to reduce Re transmuta- tion down to ~2 at.% (and 0.2 at.% Os). The quasi-static fracture mechanical experiments were carried out following ASTM E399 aiming at the determination of plane strain fracture toughness K Ic . The post irradiation examination of the specimens irradiated at 800 °C reveals severe material embrittlement. At T test = T irr = 800 °C, a deformation free brittle fracture is observed. The fractographic investigations show a mixture of brittle transgranular cleavage and intergranular fracture. With increasing the test tempera- ture above 10 0 0 °C, the fracture mode is changed from the brittle to a ductile one. Blunting of the notch tip leads to a suppression of the crack initiation and propagation and consequently no failure of the spec- imens was observed up to severe deflection levels. In some cases, however, a ductile crack growth with a characteristic dimple formation was identified, in addition. Based on the obtained results, the Ductile to Brittle Transition Temperature shift induced by the neutron irradiation at 800 °C is evaluated to be 600-625 °C.

KW - Polycrystalline tungsten

KW - Fracture behaviour

KW - Neutron irradiation

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/42312920

U2 - 10.1016/j.jnucmat.2020.152761

DO - 10.1016/j.jnucmat.2020.152761

M3 - Article

VL - 547

SP - 1

EP - 8

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

M1 - 152761

ER -

ID: 7044198