国产核用不锈钢辐照损伤研究

doi:10.11900/0412.1961.2017.00117

金属学报

2017, Vol. 53

Issue (12): 1588-1602 DOI: 10.11900/0412.1961.2017.00117

本期目录 | 过刊浏览

国产核用不锈钢辐照损伤研究

邓平^1,², 彭群家^1,³(

), 韩恩厚¹, 柯伟¹, 孙晨³, 夏海鸿³, 焦治杰⁴

1 中国科学院金属研究所中科院核用材料与安全性评价重点实验室沈阳 110016
2 中国科学技术大学材料科学与工程学院沈阳 110016
3 国家电投集团科学技术研究院有限公司北京 102209
4 Department of Nuclear Engineering and Radiological Sciences, University of Michigan,Ann Arbor, MI 48109, U.S.A.

Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel

Ping DENG^1,², Qunjia PENG^1,³(

), En-Hou HAN¹, Wei KE¹, Chen SUN³, Haihong XIA³, Zhijie JIAO⁴

1 CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2 School of Materials Science and Engineering, University of Science and Technology of China, Shenyang 110016, China
3 State Power Investment Corporation Research Institute, Beijing 102209, China
4 Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109, U.S.A.

引用本文:

邓平, 彭群家, 韩恩厚, 柯伟, 孙晨, 夏海鸿, 焦治杰. 国产核用不锈钢辐照损伤研究[J]. 金属学报, 2017, 53(12): 1588-1602.
Ping DENG, Qunjia PENG, En-Hou HAN, Wei KE, Chen SUN, Haihong XIA, Zhijie JIAO. Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel[J]. Acta Metall Sin, 2017, 53(12): 1588-1602.

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摘要:

采用2 MeV质子束在360 ℃对国产核用304不锈钢试样进行了辐照实验,利用显微硬度仪、透射电子显微镜(TEM)和三维原子探针(3DAP)等研究了材料的辐照损伤,分析了辐照剂量对辐照损伤演化的影响规律。结果表明,304不锈钢辐照损伤微观结构以位错环和少量孔洞为主,位错环的数量密度为10²² m^-3量级,平均尺寸小于10 nm。材料在晶界和位错环处发生元素偏析,其中Cr、Ni在晶界和位错环处偏析程度相近,而Si在位错环处的偏析程度数倍于晶界。位错环平均尺寸和数量密度、晶界偏析程度以及辐照硬化程度均随辐照剂量增加而增加,并在3.0~5.0 dpa范围内趋于饱和。

关键词 ：核用不锈钢, 质子辐照, 位错环, 辐照偏析, 辐照硬化

Abstract：

The radiation-induced segregation (RIS) and microstructure evolution such as dislocation loops and cavities are major microstructural causes for the irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steel (SS) core components. While a couple of studies have been reported on the irradiation induced damage in nuclear grade (NG) austenitic SS, the evolution of dislocation loop density and size and its correlation with the mechanical properties have still remained incompletely understood. In addition, the correlation between the segregation at the grain boundary and that at the dislocation loop has received limited attentions. In particular, there is still a lack of a systematic study of the irradiation damage in domestically fabricated NG austenitic SS. In this work, the proton-irradiation induced microstructural damage in domestically fabricated 304NG SS was characterized, in an effort to correlate the RIS and the dislocation loop density and size with the irradiation dose, as well as the dislocation loop density and size with the radiation-induced hardening. The results revealed that the radiation-induced microstructure damage was mainly dislocation loops with a few micro-voids. The loop density was in the order of 10²² m^-3 with an average size of <10 nm. The square root of the product of loop density and size (Nd)^0.5, scaled linearly with the square root of irradiation dose with a factor of 6.8×10³ dpa^-0.5mm^-1. The loops were believed to be mainly responsible for the hardening in 304NG SS, which also scaled linearly with (Nd)^0.5 with a factor of 1.16×10^-2 HV_0.025mm. A comparative analysis about the segregation at the grain boundary and at the dislocation loop was conducted. While the depletion of Cr and enrichment of Ni at the dislocation loop and grain boundary showed no difference, the enrichment of Si at the dislocation loop could be of about 6 times of that at the grain boundary. In addition, the loop density and loop size, as well as RIS and radiation-induced hardening were all increased by a higher dose and tended to saturate by a dose of 3.0~5.0 dpa.

Key words： nuclear grade stainless steel proton irradiation dislocation loop radiation-induced segregation radiation-induced hardening

收稿日期: 2017-04-06

ZTFLH:

TG139.4

基金资助:科技部国际科技合作专项项目No.2014DFA50800和国家自然科学基金项目No.51571204

作者简介:

作者简介邓平,男,1989年生,博士生

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链接本文:

https://www.ams.org.cn/CN/10.11900/0412.1961.2017.00117 或 https://www.ams.org.cn/CN/Y2017/V53/I12/1588

图1 辐照试样、硬度测量位置以及TEM试样取样示意图

图2 3DAP针尖制备过程

图3 304不锈钢辐照前后的TEM明场像

图4 304不锈钢辐照前后的TEM暗场像

图5 不同辐照剂量下304不锈钢中位错环的尺寸分布

图6 位错环平均尺寸和数量密度随辐照剂量的变化

表1 304不锈钢辐照损伤结构和辐照硬化值统计

图7 不同辐照剂量下304不锈钢中孔洞的TEM明场像

图8 辐照致304不锈钢中晶界偏析分析

图9 304不锈钢经3.0 dpa辐照后晶内偏析的3DAP分析

图10 304不锈钢经3.0 dpa辐照后晶内偏析的3DAP等浓度面分析

图11 位错环处成分偏析的3DAP分析结果

图12 显微硬度随辐照剂量变化和辐照硬化与辐照剂量的关系

图13 位错环数量密度和直径乘积的平方根(Nd)0.5随辐照剂量的变化

图14 辐照致晶界偏析示意图

图15 晶界和位错环处元素偏析含量及位错环处元素偏析量与晶界处偏析量比值

图16 辐照硬化值ΔH随位错环数量密度和直径乘积的平方根(Nd)0.5的变化

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