Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites

The microstructure and mechanical properties of pure W, sintered and swaged W-1.5ZrO<sub>2</sub> composites after 1.5 × 10<sup>15</sup> Au<sup>+</sup>/cm<sup>2</sup> radiation at room temperature were characterized to investigate the impact of the ZrO&...

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Main Authors: Bo Cui, Chunyang Luo, Xiaoxi Chen, Chengqin Zou, Muhong Li, Liujie Xu, Jijun Yang, Xianfu Meng, Haibin Zhang, Xiaosong Zhou, Shuming Peng, Huahai Shen
Format: Article
Language:English
Published: MDPI AG 2022-03-01
Series:Materials
Subjects:
Online Access:https://www.mdpi.com/1996-1944/15/6/1985
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author Bo Cui
Chunyang Luo
Xiaoxi Chen
Chengqin Zou
Muhong Li
Liujie Xu
Jijun Yang
Xianfu Meng
Haibin Zhang
Xiaosong Zhou
Shuming Peng
Huahai Shen
author_facet Bo Cui
Chunyang Luo
Xiaoxi Chen
Chengqin Zou
Muhong Li
Liujie Xu
Jijun Yang
Xianfu Meng
Haibin Zhang
Xiaosong Zhou
Shuming Peng
Huahai Shen
author_sort Bo Cui
collection DOAJ
description The microstructure and mechanical properties of pure W, sintered and swaged W-1.5ZrO<sub>2</sub> composites after 1.5 × 10<sup>15</sup> Au<sup>+</sup>/cm<sup>2</sup> radiation at room temperature were characterized to investigate the impact of the ZrO<sub>2</sub> phase on the irradiation resistance mechanism of tungsten materials. It can be concluded that the ZrO<sub>2</sub> phase near the surface consists of two irradiation damage layers, including an amorphous layer and polycrystallization regions after radiation. With the addition of the ZrO<sub>2</sub> phase, the total density and average size of dislocation loops, obviously, decrease, attributed to the reason that many more glissile 1/2<111> loops migrate to annihilate preferentially at precipitate interfaces with a higher sink strength of 7.8 × 10<sup>14</sup> m<sup>−</sup><sup>2</sup><sub>.</sub> The swaged W-1.5ZrO<sub>2</sub> alloys have a high enough density of precipitate interfaces and grain boundaries to absorb large numbers of irradiated dislocations. This leads to the smallest irradiation hardening change in hardness of 4.52 Gpa, which is far superior to pure W materials. This work has a collection of experiments and conclusions that are of crucial importance to the materials and nuclear communities.
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spelling doaj.art-98b79009f2ba42e89275d0584cb152492023-11-30T21:17:03ZengMDPI AGMaterials1996-19442022-03-01156198510.3390/ma15061985Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W CompositesBo Cui0Chunyang Luo1Xiaoxi Chen2Chengqin Zou3Muhong Li4Liujie Xu5Jijun Yang6Xianfu Meng7Haibin Zhang8Xiaosong Zhou9Shuming Peng10Huahai Shen11Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaHenan Engineering Research Center for Wear of Materials, Henan University of Science and Technology, Luoyang 471003, ChinaKey Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaInstitute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, ChinaThe microstructure and mechanical properties of pure W, sintered and swaged W-1.5ZrO<sub>2</sub> composites after 1.5 × 10<sup>15</sup> Au<sup>+</sup>/cm<sup>2</sup> radiation at room temperature were characterized to investigate the impact of the ZrO<sub>2</sub> phase on the irradiation resistance mechanism of tungsten materials. It can be concluded that the ZrO<sub>2</sub> phase near the surface consists of two irradiation damage layers, including an amorphous layer and polycrystallization regions after radiation. With the addition of the ZrO<sub>2</sub> phase, the total density and average size of dislocation loops, obviously, decrease, attributed to the reason that many more glissile 1/2<111> loops migrate to annihilate preferentially at precipitate interfaces with a higher sink strength of 7.8 × 10<sup>14</sup> m<sup>−</sup><sup>2</sup><sub>.</sub> The swaged W-1.5ZrO<sub>2</sub> alloys have a high enough density of precipitate interfaces and grain boundaries to absorb large numbers of irradiated dislocations. This leads to the smallest irradiation hardening change in hardness of 4.52 Gpa, which is far superior to pure W materials. This work has a collection of experiments and conclusions that are of crucial importance to the materials and nuclear communities.https://www.mdpi.com/1996-1944/15/6/1985W alloysirradiation effectmicrostructure evolutionmechanical properties
spellingShingle Bo Cui
Chunyang Luo
Xiaoxi Chen
Chengqin Zou
Muhong Li
Liujie Xu
Jijun Yang
Xianfu Meng
Haibin Zhang
Xiaosong Zhou
Shuming Peng
Huahai Shen
Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
Materials
W alloys
irradiation effect
microstructure evolution
mechanical properties
title Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
title_full Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
title_fullStr Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
title_full_unstemmed Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
title_short Superior Radiation Resistance of ZrO<sub>2</sub>-Modified W Composites
title_sort superior radiation resistance of zro sub 2 sub modified w composites
topic W alloys
irradiation effect
microstructure evolution
mechanical properties
url https://www.mdpi.com/1996-1944/15/6/1985
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