金属学报  2012, Vol. 48 Issue (6): 753-758    DOI: 10.3724/SP.J.1037.2011.00668

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富Cu团簇的析出对RPV模拟钢韧-脆转变温度的影响

徐刚1,蔡琳玲1,冯柳1,周邦新1,2,王均安2,张海生3

1. 上海大学材料研究所, 上海 200072 2. 上海大学微结构重点实验室, 上海 200444 3. 中国核动力研究设计院核燃料及材料国家重点实验室, 成都 610041

EFFECT OF THE PRECIPITATION OF Cu-RICH CLUSTERS ON THE DBTT OF RPV SIMULATED STEEL

XU Gang1, CAI Linling1, FENG Liu1, ZHOU Bangxin1,2,WANG Jun'an1,2,ZHANG Haisheng3

1. Institute of Materials, Shanghai University, Shanghai 200072 2. Laboratory for Microstructures, Shanghai University, Shanghai 200444 3. National Key Laboratory for Nuclear Fuel and Materials, Nuclear Power Institute of China, Chengdu 610041

徐刚,蔡琳玲,冯柳,周邦新,王均安,张海生. 富Cu团簇的析出对RPV模拟钢韧-脆转变温度的影响[J]. 金属学报, 2012, 48(6): 753-758.
, , , , , . EFFECT OF THE PRECIPITATION OF Cu-RICH CLUSTERS ON THE DBTT OF RPV SIMULATED STEEL[J]. Acta Metall Sin, 2012, 48(6): 753-758.

摘要 参考文献 相关文章 Metrics 全文: PDF(1181 KB)   摘要: 将Cu含量高于实际核反应堆压力容器(RPV)钢的模拟钢在880 ℃水淬后,在660 ℃进行 调质处理, 然后在370 ℃时效不同时间, 采用TEM,原子探针层析法(APT)和冲击实验对其进行研究. 结果表明, 时效1150 h后,富Cu团簇的析出仍处于形核阶段, 对韧-脆转变温度(DBTT)没有明显的影响;时效3000 h后, 试样中析出了平均尺寸为1.5 nm的富Cu团簇, 主要分布在位错线上,数量密度达到4.2×1022 m-3, DBTT由调质处理后的-100 ℃升高至-60 ℃; 时效13200 h后, 富Cu团簇略有长大, 平均尺寸达到2.4 nm,团簇的数量密度与时效3000 h的试样处于相同数量级, DBTT升高至-45 ℃.采用热时效方法使富Cu团簇析出后, DBTT只提高了55 ℃, 没有中子辐照引起的那样显著, 这不仅是因为富Cu团簇的数量密度低, 基体中没有中子辐照产生的晶体缺陷也是重要的原因. 关键词 ： 核压力容器模拟钢,  韧-脆转变温度,  富Cu团簇,  原子探针层析法     Abstract：Reactor pressure vessels (RPVs) are usually made of low alloy ferritic steels, among which A508-III steel is a typical one. The long--term neutron irradiation can induce the embrittlement of RPV steels, and the embrittlement may lead to a reduction of the RPV service life. Generally, this behavior of the embrittlement is well established and is typically assessed by the increase in the ductile-to-brittle transition temperature (DBTT) of the RPV steels. For many years, extensive studies have revealed that irradiation-induced ultrafine Cu-rich clusters (CRCs) play an important role and CRCs with high number density cause hardening and embrittlement of the RPV steels. In order to investigate the effect of the precipitation of CRCs on DBTT of RPV steels by thermal aging, it is necessary to increase the Cu content in RPV steel. A 40 kg ingot of RPV simulated steel based on the composition of A508--III steel with higher Cu content (0.6% in mass fraction) was prepared by vacuum induction melting, and it was forged and hot rolled to a plate with 7 mm in thickness. Specimens with a dimension of 7 mm×12 mm×60 mm were cut from the hot--rolled plate. The heat treatment routes of the specimens consists of a soaking at 880℃ for 0.5 h, a water quenching, a tempering at 660℃ for 10 h, and a final aging at 370℃ for various times. The effect of the precipitation of CRCs on the DBTT of the RPV simulated steel was investigated by Charpy impact tests, as well as the microstructure analysis was carried out by TEM and atom probe tomography (APT). According to ASME 23 standard, Charpy-V specimens with a dimension of 5 mm×10 mm×55 mm were prepared and tested by TINIUS OLSEN 84 impact test machine. The TEM analysis shows that CRCs precipitate on dislocations in the specimen aged at 370 ℃ for 3000 h, and the clusters become a little coarsened when the aging time is extended to 13200 h. For the specimens aged for 1150 h, CRCs were on the stage of the nucleation assessed by TEM as well as APT analysis, and they did not have an effect on the DBTT of the RPV simulated steel. For the specimens aged for 3000 h, CRCs precipitated with an average equivalent diameter of 1.5 nm and a number density of 4.2×1022 m-3, and it results in the increase of the DBTT from -100 ℃ to -60 ℃. For the specimens aged for 13200 h, CRCs slightly coarsened to 2.4 nm of the average equivalent diameter, while the number density is similar to that of the specimens aged for 3000 h. In this case the DBTT rose to -45 ℃. Therefore, the present work shows the precipitation of CRCs induced by thermal aging reveals a smaller impact on the DBTT than that by neutron irradiation. From the thermal aging aspect, the much lower number density of CRCs and the absence of the defects induced by neutron irradiation in the matrix could account for this phenomenon. Key words： reactor pressure vessel simulated steel    ductile-to-brittle transformation temperature    Cu-rich cluster    atom probe tomography 收稿日期: 2011-10-25      ZTFLH:  TL341   基金资助: 国家重点基础研究发展计划项目2011CB610503, 国家自然科学基金项目50931003和上海市重点学科建设项目S30107资助 作者简介: 徐刚, 男, 1978年生, 博士生 服务 把本文推荐给朋友 加入引用管理器 E-mail Alert RSS 作者相关文章 徐刚 蔡琳玲 冯柳 周邦新 王均安 张海生 44.8K 链接本文: https://www.ams.org.cn/CN/10.3724/SP.J.1037.2011.00668      或      https://www.ams.org.cn/CN/Y2012/V48/I6/753 [1] Toyama T, Nagai Y, Tang Z, Hasegawa M, Almazouzi A, van Walle E,Gerard R.  Acta Mater, 2007; 55: 6852 [2] Auger P, Pareige P, Welzel S, van Duysen J C.  J Nucl Mater,2000; 280: 331 [3] Miller M K, Russell K F, Sokolov M A, Nanstad R K.  J Nucl Mater,2007; 361: 248 [4] Miller M K, Russell K F, Sokolov M A, Nanstad R K.  J Nucl Mater,2003; 320: 177 [5] Miller M K, Nanstad P K, Sokolov M A, Russell K F.  J Nucl Mater,2006; 351: 216 [6] Phythian W J, English C A.  J Nucl Mater, 1993; 205: 162 [7] Carter R G, Soneda N, Dohi K, Hyde J M, English C A, Server W L. 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