材料輻照損傷中的點缺陷團簇與一維遷移現象

萬發榮

doi:10.13374/j.issn2095-9389.2020.02.05.001

材料輻照損傷中的點缺陷團簇與一維遷移現象

doi: 10.13374/j.issn2095-9389.2020.02.05.001

萬發榮^,

北京科技大學材料科學與工程學院，北京 100083

基金項目: 國家自然科學基金資助項目（11875085，51471026）；國家磁約束核聚變能發展研究專項（ITER計劃國內專項）資助項目（2014GB120000）

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通訊作者:
E-mail：wanfr@mater.ustb.edu.cn

中圖分類號: TG111.2
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出版歷程
- 收稿日期: 2020-02-02
- 刊出日期: 2020-12-25

Clusters of point defects and one-dimensional motion of clusters during irradiation damage in materials

WAN Fa-rong^,

School of Materials Science and Engineering, University of Science and Technology Beijing, 100083 Beijing, China

More Information

Corresponding author: E-mail: wanfr@mater.ustb.edu.cn

摘要

摘要: 材料輻照損傷是核反應堆材料、尤其是核聚變堆材料所面臨的重要問題。高能粒子（中子、離子、電子）輻照在材料中會產生大量的點缺陷，即自間隙原子和空位。這些點缺陷聚集在一起會形成自間隙原子團簇和空位團簇，從而對材料結構和性能的演化產生重要影響。空位團簇包括有空洞、層錯四面體、空位型位錯環，而自間隙原子團簇則只有自間隙型位錯環。本文介紹了兩種點缺陷團簇的性質、及其對于以材料輻照腫脹為主要內容的材料輻照損傷性能的影響。作為空位團簇，比較詳細介紹了具有本課題組特色的空位型位錯環的研究，同時分析了合金元素和氫同位素對空位型位錯環的影響。在鐵試樣中形成的這種空位型位錯環尺寸可達100 nm左右，該空位型位錯環具有兩種柏氏矢量， b =<100> 和 b =1/2<111>，前者的數密度比后者高一個數量級。對于自間隙原子團簇，則重點介紹了與其相關的一維遷移現象及其研究動態，該一維遷移性能有可能是影響高熵合金輻照性能的重要因素。
- 點缺陷 /
- 缺陷團簇 /
- 一維遷移 /
- 輻照損傷 /
- 核聚變堆材料
Abstract: Irradiation damage in materials for nuclear reactors, particularly for fusion reactors, is a serious problem. For example, the pressure vessel in a fission power plant becomes brittle after exposure to neutron irradiation for many years. In the case of fusion reactors, in addition to the increase in ductile-to-brittle transition temperature, irradiation-induced swelling occurs in structural materials that need to tolerate high-dose irradiation of several hundreds of displacements per atom (dpa). The irradiation of particles (such as neutrons, ions, and electrons) with high energy introduces a large number of point defects, i.e., self-interstitial atoms and vacancies, into materials. Such point defects aggregate together to form self-interstitial atom clusters as interstitial loop and vacancy clusters as void, stacking fault tetrahedra, or vacancy loop. Then, these clusters affect the microstructure and properties of materials. Moreover, these clusters play a more important role than individual point defects during the irradiation damage process. Even after research for decades, many questions about clusters remain unanswered partially because of the difficulties in irradiation test and cluster observation. This review paper explained the structures of clusters and the effect of clusters on irradiation damage in materials. As a unique research of this author’s group, the formation of vacancy-type dislocation loops with sizes of up to 100 nm in iron was introduced, including the effect of hydrogen and its isotope and the effect of alloy elements on the formation of vacancy-type dislocation loops. There are two different kinds of vacancy-type dislocation loops, i.e., those having a Burgers vector of b =<100> and those having a Burgers vector of b =1/2<111>. The density of the first type is approximately one order of magnitude higher than that of the second type. The one-dimensional motion of self-interstitial atom clusters and the research activities in this field were also discussed in detail, and the one-dimensional motion would be a key factor effecting the irradiation damage of high entropy alloys.
- point defect /
- defect cluster /
- one-dimension motion /
- irradiation damage /
- materials for a fusion reactor

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圖 1 電子束輻照時的位錯環變化

Figure 1. Change of dislocation loops under electron irradiation

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圖 2 級聯過程中的自間隙原子團簇的一維遷移

Figure 2. One-dimensional motion of self-interstitial atom clusters during the cascade process

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