奥氏体不锈钢辐照肿胀和偏析的研究进展

doi:10.11896/cldb.20070198

材料导报

2021, Vol. 35

Issue (5): 5122-5129 https://doi.org/10.11896/cldb.20070198

金属与金属基复合材料

奥氏体不锈钢辐照肿胀和偏析的研究进展

李连奇, 杨占兵

北京科技大学冶金与生态工程学院,北京 100083

Research Progress on Void Swelling and Radiation-induced Segregation of Austenitic Stainless Steel

LI Lianqi, YANG Zhanbing

School of Metallurgical and Ecological Engineering, University of Science and Technology Beijing, Beijing 100083, China

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摘要随着社会对能源需求的增加,核能作为一种可大规模替代传统化石能源的清洁能源备受关注。目前我国正在大力推动第四代先进核反应堆技术的研发,这对反应堆结构材料的性能提出了更高的要求。
由于反应堆堆芯的强烈辐照,作为堆芯结构材料的奥氏体不锈钢长期服役会发生辐照损伤现象,尤其是辐照肿胀和偏析,威胁反应堆运营安全。
研究发现,奥氏体不锈钢的辐照肿胀和偏析现象与辐照剂量、辐照温度、合金元素成分等密切相关。对于辐照肿胀,常用冷加工和添加合金元素等方法进行控制,其中15-15Ti奥氏体不锈钢能够承受大于100 dpa的辐照剂量,被选为快堆候选包壳材料。但这两种方法开发的奥氏体不锈钢仍未达到先进核反应堆对奥氏体不锈钢抗辐照性能的要求,为此需要对控制所有辐照损伤效应的点缺陷的扩散行为进行更深入的系统和实验分析,以深入理解辐照肿胀现象。对于辐照偏析,其产生机制一直存在争议,主要有空位机制和间隙原子机制两种观点,但奥氏体不锈钢的辐照偏析很可能是这两种机制混合控制的结果,为此仍需进一步建立更优化的动力学模型进行研究。此外,近期研究表明辐照缺陷的一维迁移现象可能与辐照损伤密切相关,但仍存在一些细节需要进一步的实验研究。
本文阐述了奥氏体不锈钢发生辐照肿胀和偏析的相关影响因素,分析了控制辐照肿胀的现有手段的不足,总结了辐照偏析发生机制的争议和相关进展,归纳了奥氏体不锈钢抗辐照性能研究存在的问题并对未来的研究方向进行了展望。

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关键词: 核反应堆材料奥氏体不锈钢辐照肿胀辐照偏析

Abstract: As society’s demand for energy increases, nuclear energy has become the focus of recent studies. China is strongly promoting the development of fourth generation nuclear reactor, which puts higher requirements on the performance of reactor structural materials.
Austenitic stainless steel, as the core structure material,will undergo radiation damage under long-term service due to the intense radiation in the reactor core, especially the void swelling and radiation-induced segregation, which threaten the safety of the reactor operation.
Void swelling and radiation-induced segregation of austenitic stainless steel are closely related to irradiation dose, irradiation temperature and alloy composition.Cold working and alloy elements are usually used to control void swelling. The 15-15Ti austenitic stainless steel shows potential for cladding of fast breeder reactor due to withstanding radiation doses over 100 dpa. However, the austenitic stainless steels developed by these two methods have not fully satisfied the requirement for service. Point defects govern the radiation damage effects; therefore, a more in-depth syste-matic and experimental analysis on the diffusion behavior of point defects is essential to understand the void swelling. Two controversial views were proposed on the mechanism of radiation-induced segregation, that is, vacancy mechanism and interstitial atomic mechanism. However, the radiation-induced segregation of austenitic stainless steel may be governed by both; subsequently, a more optimized kinetic model needs to be established for further study. In addition, recent studies show that the one dimension motion of radiation defects is related to radiation damage, but further research is essential to explore some experimental details.
In the present paper, we review the influence factors of void swelling and radiation-induced segregation of austenitic stainless steel, the shortcomings of the existing controlling methods of void swelling, and the progress on the mechanism of radiation-induced segregation. Finally, we prospect the future research directions according to the existing problems of study on the anti-irradiation property of austenitic stainless steel.

Key words: materials in nuclear reactor austenitic stainless steel void swelling radiation-induced segregation

出版日期: 2021-03-10 发布日期: 2021-03-12

ZTFLH:

TL341

基金资助: 国家自然科学基金(51471027)

通讯作者: yangzhanbing@ustb.edu.cn

作者简介: 李连奇,2018年7月毕业于北京科技大学,获得工学学士学位。现为北京科技大学冶金与生态工程学院硕士研究生,在杨占兵副教授的指导下进行研究。目前主要研究领域为奥氏体不锈钢的辐照损伤。
杨占兵,北京科技大学冶金与生态工程学院副教授,硕士研究生导师。2001年7月本科毕业于北京科技大学材料科学与工程学院,2008年1月在北京科技大学冶金与生态工程学院冶金工程物理化学系取得博士学位,2008—2014年在日本北海道大学工学部能源-材料融合领域研究中心进行博士后研究工作。2014年3月起担任北京科技大学冶金与生态工程学院物理化学系副教授,主要从事高能粒子辐照条件下金属晶体中的非平衡现象及其动力学过程以及钢中夹杂物控制的研究工作,在国内外期刊上发表论文70余篇。

引用本文:

李连奇, 杨占兵. 奥氏体不锈钢辐照肿胀和偏析的研究进展[J]. 材料导报, 2021, 35(5): 5122-5129.
LI Lianqi, YANG Zhanbing. Research Progress on Void Swelling and Radiation-induced Segregation of Austenitic Stainless Steel. Materials Reports, 2021, 35(5): 5122-5129.

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http://www.mater-rep.com/CN/10.11896/cldb.20070198 或 http://www.mater-rep.com/CN/Y2021/V35/I5/5122

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