Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation

Xiaoou Yi; Lei Zhang; Wentuo Han; Jiao Chen; Pingping Liu; Yanwei Lv; Jiupeng Song; Luwei Xue; Diancheng Geng; Kenta Yoshida; Takeshi Toyama; Qian Zhan; Farong Wan; Somei Ohnuki; Yasuyoshi Nagai

doi:10.1016/j.ijrmhm.2019.105004

Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation

Xiaoou Yi, Lei Zhang, Wentuo Han, Jiao Chen, Pingping Liu, Yanwei Lv, Jiupeng Song, Luwei Xue, Diancheng Geng, Kenta Yoshida, Takeshi Toyama, Qian Zhan, Farong Wan, Somei Ohnuki, Yasuyoshi Nagai

Research output: Contribution to journal › Article › peer-review

3 Citations (Scopus)

Abstract

Ultra-high purity (> 99.9999 wt%) chemical vapour deposited tungsten (CVD–W) samples were neutron irradiated in the BR2 reactor (Belgium) at T_irr < 210 °C to ~ 0.15 dpa, followed by isochronal annealing at 500, 800 and 1100 °C. Defect characterization showed that dislocation loops dominated the as-irradiated damage microstructure and were mostly ≤5 nm. Void formation was observed after post-irradiation annealing at 1100 °C. The mechanical and thermal properties of CVD-W were evaluated based on tensile tests, Vickers hardness and temperature wave analysis. Fractography study suggested that a transition from intergranular fracture to cleavage fracture took place in the material after neutron irradiation. Hardening was found ~ 23% after irradiation. Subsequent annealing below 800 °C saw further increase in hardness, featuring a maximum value of about Hv = 487. Softening occurred at 1100 °C. Thermal diffusivity dropped by ~ 65% after irradiation and ~ 40% of this degradation recovered at 1100 °C.

Original language	English
Article number	105004
Journal	International Journal of Refractory Metals and Hard Materials
Volume	85
DOIs	https://doi.org/10.1016/j.ijrmhm.2019.105004
Publication status	Published - 2019 Dec

Keywords

CVD-W
Defects
Mechanical properties
Neutron irradiation
Thermal properties

ASJC Scopus subject areas

Ceramics and Composites
Mechanics of Materials
Mechanical Engineering
Metals and Alloys
Materials Chemistry

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Yi, X., Zhang, L., Han, W., Chen, J., Liu, P., Lv, Y., Song, J., Xue, L., Geng, D., Yoshida, K., Toyama, T., Zhan, Q., Wan, F., Ohnuki, S., & Nagai, Y. (2019). Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation. International Journal of Refractory Metals and Hard Materials, 85, [105004]. https://doi.org/10.1016/j.ijrmhm.2019.105004

Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation. / Yi, Xiaoou; Zhang, Lei; Han, Wentuo; Chen, Jiao; Liu, Pingping; Lv, Yanwei; Song, Jiupeng; Xue, Luwei; Geng, Diancheng; Yoshida, Kenta ; Toyama, Takeshi; Zhan, Qian; Wan, Farong; Ohnuki, Somei; Nagai, Yasuyoshi.

In: International Journal of Refractory Metals and Hard Materials, Vol. 85, 105004, 12.2019.

Research output: Contribution to journal › Article › peer-review

Yi, X, Zhang, L, Han, W, Chen, J, Liu, P, Lv, Y, Song, J, Xue, L, Geng, D, Yoshida, K , Toyama, T, Zhan, Q, Wan, F, Ohnuki, S & Nagai, Y 2019, 'Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation', International Journal of Refractory Metals and Hard Materials, vol. 85, 105004. https://doi.org/10.1016/j.ijrmhm.2019.105004

Yi, Xiaoou ; Zhang, Lei ; Han, Wentuo ; Chen, Jiao ; Liu, Pingping ; Lv, Yanwei ; Song, Jiupeng ; Xue, Luwei ; Geng, Diancheng ; Yoshida, Kenta ; Toyama, Takeshi ; Zhan, Qian ; Wan, Farong ; Ohnuki, Somei ; Nagai, Yasuyoshi. / Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation. In: International Journal of Refractory Metals and Hard Materials. 2019 ; Vol. 85.

@article{afe08471fc0646b98c25e8102babb329,

title = "Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation",

abstract = "Ultra-high purity (> 99.9999 wt%) chemical vapour deposited tungsten (CVD–W) samples were neutron irradiated in the BR2 reactor (Belgium) at Tirr < 210 °C to ~ 0.15 dpa, followed by isochronal annealing at 500, 800 and 1100 °C. Defect characterization showed that dislocation loops dominated the as-irradiated damage microstructure and were mostly ≤5 nm. Void formation was observed after post-irradiation annealing at 1100 °C. The mechanical and thermal properties of CVD-W were evaluated based on tensile tests, Vickers hardness and temperature wave analysis. Fractography study suggested that a transition from intergranular fracture to cleavage fracture took place in the material after neutron irradiation. Hardening was found ~ 23% after irradiation. Subsequent annealing below 800 °C saw further increase in hardness, featuring a maximum value of about Hv = 487. Softening occurred at 1100 °C. Thermal diffusivity dropped by ~ 65% after irradiation and ~ 40% of this degradation recovered at 1100 °C.",

keywords = "CVD-W, Defects, Mechanical properties, Neutron irradiation, Thermal properties",

author = "Xiaoou Yi and Lei Zhang and Wentuo Han and Jiao Chen and Pingping Liu and Yanwei Lv and Jiupeng Song and Luwei Xue and Diancheng Geng and Kenta Yoshida and Takeshi Toyama and Qian Zhan and Farong Wan and Somei Ohnuki and Yasuyoshi Nagai",

note = "Funding Information: Post-irradiation experiments on CVD-W were conducted at the International Research Center for Nuclear Materials Science (Oarai) , Institute for Materials Research (IMR) , Tohuku University . The authors thank the IMR staff for their kind assistance with PIE work. X. Yi acknowledges funding support from the National Natural Science Foundation of China via grant No. 51701014 . Funding Information: Post-irradiation experiments on CVD-W were conducted at the International Research Center for Nuclear Materials Science (Oarai), Institute for Materials Research (IMR), Tohuku University. The authors thank the IMR staff for their kind assistance with PIE work. X. Yi acknowledges funding support from the National Natural Science Foundation of China via grant No. 51701014. Publisher Copyright: {\textcopyright} 2019 Elsevier Ltd",

year = "2019",

month = dec,

doi = "10.1016/j.ijrmhm.2019.105004",

language = "English",

volume = "85",

journal = "International Journal of Refractory Metals and Hard Materials",

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TY - JOUR

T1 - Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation

AU - Yi, Xiaoou

AU - Zhang, Lei

AU - Han, Wentuo

AU - Chen, Jiao

AU - Liu, Pingping

AU - Lv, Yanwei

AU - Song, Jiupeng

AU - Xue, Luwei

AU - Geng, Diancheng

AU - Yoshida, Kenta

AU - Toyama, Takeshi

AU - Zhan, Qian

AU - Wan, Farong

AU - Ohnuki, Somei

AU - Nagai, Yasuyoshi

N1 - Funding Information: Post-irradiation experiments on CVD-W were conducted at the International Research Center for Nuclear Materials Science (Oarai) , Institute for Materials Research (IMR) , Tohuku University . The authors thank the IMR staff for their kind assistance with PIE work. X. Yi acknowledges funding support from the National Natural Science Foundation of China via grant No. 51701014 . Funding Information: Post-irradiation experiments on CVD-W were conducted at the International Research Center for Nuclear Materials Science (Oarai), Institute for Materials Research (IMR), Tohuku University. The authors thank the IMR staff for their kind assistance with PIE work. X. Yi acknowledges funding support from the National Natural Science Foundation of China via grant No. 51701014. Publisher Copyright: © 2019 Elsevier Ltd

PY - 2019/12

Y1 - 2019/12

N2 - Ultra-high purity (> 99.9999 wt%) chemical vapour deposited tungsten (CVD–W) samples were neutron irradiated in the BR2 reactor (Belgium) at Tirr < 210 °C to ~ 0.15 dpa, followed by isochronal annealing at 500, 800 and 1100 °C. Defect characterization showed that dislocation loops dominated the as-irradiated damage microstructure and were mostly ≤5 nm. Void formation was observed after post-irradiation annealing at 1100 °C. The mechanical and thermal properties of CVD-W were evaluated based on tensile tests, Vickers hardness and temperature wave analysis. Fractography study suggested that a transition from intergranular fracture to cleavage fracture took place in the material after neutron irradiation. Hardening was found ~ 23% after irradiation. Subsequent annealing below 800 °C saw further increase in hardness, featuring a maximum value of about Hv = 487. Softening occurred at 1100 °C. Thermal diffusivity dropped by ~ 65% after irradiation and ~ 40% of this degradation recovered at 1100 °C.

AB - Ultra-high purity (> 99.9999 wt%) chemical vapour deposited tungsten (CVD–W) samples were neutron irradiated in the BR2 reactor (Belgium) at Tirr < 210 °C to ~ 0.15 dpa, followed by isochronal annealing at 500, 800 and 1100 °C. Defect characterization showed that dislocation loops dominated the as-irradiated damage microstructure and were mostly ≤5 nm. Void formation was observed after post-irradiation annealing at 1100 °C. The mechanical and thermal properties of CVD-W were evaluated based on tensile tests, Vickers hardness and temperature wave analysis. Fractography study suggested that a transition from intergranular fracture to cleavage fracture took place in the material after neutron irradiation. Hardening was found ~ 23% after irradiation. Subsequent annealing below 800 °C saw further increase in hardness, featuring a maximum value of about Hv = 487. Softening occurred at 1100 °C. Thermal diffusivity dropped by ~ 65% after irradiation and ~ 40% of this degradation recovered at 1100 °C.

KW - CVD-W

KW - Defects

KW - Mechanical properties

KW - Neutron irradiation

KW - Thermal properties

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DO - 10.1016/j.ijrmhm.2019.105004

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AN - SCOPUS:85071437138

VL - 85

JO - International Journal of Refractory Metals and Hard Materials

JF - International Journal of Refractory Metals and Hard Materials

SN - 0958-0611

M1 - 105004

ER -

Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation

Abstract

Keywords

ASJC Scopus subject areas

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