应力加载条件下316L奥氏体钢在液态锂铅合金中的腐蚀行为

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Masatoshi Kondo , Yota Koike , Kenshi Ohno , Kaoru Omiya , Minho Oh , Naoko Oono-Hori
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引用次数: 0

摘要

材料相容性是聚变反应堆液态LiPb包层发展的重要问题之一。通过将c环试样分别浸泡在573 K和773 K的LiPb液中1000 h,研究了316L奥氏体钢在573 K的LiPb液中的腐蚀特性。无论拉伸应力载荷如何,316L奥氏体钢在LiPb液中的腐蚀都很小。腐蚀是由于合金元素(即Fe, Cr和Ni)在773 K下暴露于LiPb液体中而不进行拉伸应力加载而在试样表面溶解造成的。腐蚀过程中,作为奥氏体稳定元素的Ni的损耗导致表面由奥氏体fcc组织向铁素体bcc组织转变。在100mpa和200mpa的拉伸应力作用下,c形环试样顶端附近区域的溶解腐蚀得到缓解。在拉伸应变区检测到富Cr区和富C区,可作为LiPb液体的防腐层。由于在液态LiPb中,Cr的溶解度小于Fe和Ni,因此表面Fe和Ni的损耗导致了Cr的富集。表面渗碳可以减缓Cr的溶解。应力诱导的马氏体相变和位错的引入有助于富Cr区和富C区的形成。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Corrosion behavior of 316L austenitic steel in liquid lithium lead alloy under stress loading conditions

Corrosion behavior of 316L austenitic steel in liquid lithium lead alloy under stress loading conditions
The material compatibility is one of the important issues for the development of liquid LiPb blanket of fusion reactors. The corrosion characteristics of 316L austenitic steel under tensile stress loadings were investigated by means of the immersion of C-ring specimens into liquid LiPb at 573 K and 773 K for 1000 h. The corrosion of 316L austenitic steel was negligibly small in liquid LiPb at 573 K regardless of the tensile stress loadings. The corrosion was caused by the dissolution of alloying elements (i.e., Fe, Cr and Ni) on the surface of specimens exposed to liquid LiPb at 773 K without the tensile stress loadings. The phase transformation from fcc structure of austenite to bcc structure of ferrite was induced on the surface according to the depletion of Ni in the corrosion procedure, which was austenite-stabilizing element. The dissolution corrosion was mitigated on the area around the apex of the C-ring specimens where the tensile stresses of 100 MPa and 200 MPa were applied. Cr- and C- rich regions were detected on the tensile-strained area of the specimens which could function as an anti-corrosion layer in liquid LiPb. The enrichment of Cr was induced by the depletion of Fe and Ni on the surface since the solubility of Cr was smaller than that of Fe and Ni in liquid LiPb. The dissolution of Cr could be mitigated by the carburization on the surface. The stress-induced martensitic transformation and the introduction of dislocations could contribute the formation of Cr- and C- rich regions.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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