Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550 °C with 10−7mass% dissolved oxygen

Author:

Tsisar Valentyn,Schroer Carsten,Wedemeyer Olaf,Skrypnik Aleksandr,Konys Jürgen

Funder

Nuclear Safety program of KIT

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference35 articles.

1. Power reactors and sub-critical blanket systems with lead and lead-bismuth as coolant and/or target material, International Atomic Energy Agency, Vienna (Austria) IAEA-TECDOC 1348, 2003.

2. G.M. Griaznov, V.A. Evtikhin, L.P. Zavialskiy, et al. Material Science of Liquid Metal Systems of Thermonuclear Reactors, Energoatomizdat, Moscow, 1989, 240 p. (in Russian).

3. Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermalhydraulics and Technologies, 2007 Edition, OECD, NEA No. 6195, ISBN 978-92-64-99002-9.

4. Corrosion behavior of steels in flowing lead–bismuth

5. Temperature effect on the corrosion mechanism of austenitic and martensitic steels in lead–bismuth

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