| ODS钢液态重金属环境腐蚀研究进展 |
| |
| 引用本文： | 赵熹,曾献,张勇,燕青芝,陈映雪,殷振国. ODS钢液态重金属环境腐蚀研究进展[J]. 机械工程学报, 2020, 56(21): 1-10. DOI: 10.3901/JME.2020.21.001 |
| |
| 作者姓名： | 赵熹 曾献 张勇 燕青芝 陈映雪 殷振国 |
| |
| 作者单位： | 1. 中广核研究院有限公司 深圳 518031;2. 北京科技大学材料科学与工程学院 北京 100083;3. 中国科学技术大学物理学院 合肥 230026 |
| |
| 基金项目： | 中广核先进核能战略专项资助项目 |
| |
| 摘 要： | 铅基快堆(Lead-cooled fast reactor,LFR)采用液态重金属(铅/铅铋合金)作为冷却剂,具有高安全性、高经济性等特点,并且在核能可持续发展方面具有一定的优势,目前被列为第四代核能系统六种参考堆型之一。液态金属冷却剂在服役过程中具有高温、高流速和高密度等特点,会对堆芯结构材料产生严重的腐蚀破坏。纳米氧化物弥散强化钢(Oxide dispersion strengthened steel,ODS)具有优异的抗辐照性能和优良的高温力学性能,目前已经成为先进快中子反应堆堆芯候选结构材料研究热点,其抗液态金属冷却剂腐蚀的能力是影响反应堆安全运行的关键性能之一。对目前有代表性的ODS钢在液态重金属环境中的腐蚀研究进展进行了综述,并结合ODS钢在氧化性气体环境和超临界水中的氧化腐蚀研究进展,对影响ODS钢液态金属腐蚀行为的因素进行了讨论。
|
| 关 键 词： | 铅基快堆 液态重金属 ODS钢 腐蚀行为 |
| 收稿时间： | 2019-12-09 |
Research Progress of ODS Steels Corrosion in Heavy Liquid Metal Environment |
| |
| ZHAO Xi,ZENG Xian,ZHANG Yong,YAN Qingzhi,CHEN Yingxue,YIN Zhenguo. Research Progress of ODS Steels Corrosion in Heavy Liquid Metal Environment[J]. Chinese Journal of Mechanical Engineering, 2020, 56(21): 1-10. DOI: 10.3901/JME.2020.21.001 |
| |
| Authors: | ZHAO Xi ZENG Xian ZHANG Yong YAN Qingzhi CHEN Yingxue YIN Zhenguo |
| |
| Affiliation: | 1. China Nuclear Power Technology Research Institute, Shenzhen 518031;2. School of Materials Science and Engineering, University of Science and Technology, Beijing 100083;3. School of Physical Sciences, University of Science and Technology of China, Hefei 230026 |
| |
| Abstract: | Lead-cooled fast reactor (LFR) has been selected as one of the six reactor concepts in the generation IV technology roadmap. The LFR system's enhanced safety and economic performance are of great importance for the choice of a next-generation nuclear system. However,the structural materials of reactor core suffer serious corrosion damage caused by LFR's coolant-heavy liquid metal due to the high density,high flowing rate and high temperature during operation. Oxide dispersion strengthened (ODS) steel,which has excellent irradiation resistance and high temperature mechanical behavior,has been selected as candidate structural material of the advanced fast neutron reactor. The compatibility of ODS steel in contact with heavy liquid metal is one of the key characteristics for the safety of LFR system. The current research progress of ODS steels corrosion in heavy liquid metal environment is reviewed. The factors affecting the corrosion behavior in liquid metal are discussed combined with the oxidation corrosion results in oxidizing gas mixture and supercritical water environment. |
| |
| Keywords: | lead-cooled fast reactor heavy liquid metal ODS steel corrosion behavior |
| 本文献已被 万方数据 等数据库收录！ |
| 点击此处可从《机械工程学报》浏览原始摘要信息 |
|
点击此处可从《机械工程学报》下载全文 |
|
