Behaviour Aspects of an EB-PVD Alumina (Al2O3) Film with an Interlayer (NiCrAlY) Deposited on AISI 316L Steel Investigated in Liquid Lead

Author:

Petrescu Daniel1,Nitu Alexandru1ORCID,Golgovici Florentina2ORCID,Demetrescu Ioana23ORCID,Corban Mircea4

Affiliation:

1. Institute for Nuclear Research Pitesti, POB 78, Campului Street, No. 1, 115400 Mioveni, Romania

2. Department of General Chemistry, University Politechnica of Bucharest, Splaiul Independentei Street, No. 313, 060042 Bucharest, Romania

3. Academy of Romanian Scientists, 3 Ilfov, 050094 Bucharest, Romania

4. National R&D Institute for Nonferrous and Rare Metals-IMNR, 077085 Pantelimon, Romania

Abstract

The use of lead as a primary coolant is one of the most attractive options for next-generation lead-cooled fast reactor systems (LFR). Despite many favourable features, liquid Pb is a harsh environment that induces many problems on metallic components. Therefore, candidate materials for LFR must be qualified, and the solutions to improve their properties must be found. This paper’s objective is to present the results obtained from the tensile tests of AISI 316L steel in liquid lead at 400 °C, 450 °C, and 500 °C, and the short-term corrosion tests performed on coated and uncoated AISI 316L steel at 550 °C. The coating was made of Al2O3 with a CrNiAlY interlayer using the electron beam-physical vapor deposition (EB-PVD) technique. Both the mechanical and corrosion tests were performed in stagnant lead saturated with oxygen. After testing, the specimens were characterised by several analyses, including scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDS), optical microscopy (OM), scratching test, and Vickers micro-hardness test. The tensile test results highlight the ductile behaviour of the material, and in the case of the corrosion tests, the coatings prove to be effective in protecting the substrate from the harsh environment.

Publisher

MDPI AG

Subject

General Materials Science,Metals and Alloys

Reference55 articles.

1. Addressing some issues encountered in liquid lead corrosion tests of candidate materials for future nuclear reactors;Petrescu;UPB Sci. Bull. Ser. B,2022

2. Generation IV Reactor Integrated Materials Technology Program;Corwin;Nucl. Eng. Technol.,2006

3. Yvon, P. (2016). Structural Materials for Generation IV Nuclear Reactors 2016, Woodhead Publishing.

4. Frogheri, M., Alemberti, A., and Mansani, L. (2013, January 12–17). The Advanced Lead Fast Reactor European Demonstrator (ALFRED). Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal—Hydraulics, Pisa, Italy.

5. A review of steel corrosion by liquid lead and lead-bismuth;Zhang;Corros. Sci.,2009

Cited by 1 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3