Synergistic effects of Si and Y on corrosion behavior of cast cladding steels by pre-laying Y powder for nuclear applications in static liquid LBE
Published 2022 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Synergistic effects of Si and Y on corrosion behavior of cast cladding steels by pre-laying Y powder for nuclear applications in static liquid LBE
Authors
Keywords
-
Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 566, Issue -, Pages 153781
Publisher
Elsevier BV
Online
2022-05-06
DOI
10.1016/j.jnucmat.2022.153781
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application
- (2021) Seung Gi Lee et al. Applied Sciences-Basel
- The formation mechanism and effect of amorphous SiO2 on the corrosion behaviour of Fe-Cr-Si ODS alloy in LBE at 550 °C
- (2021) Zhiyuan Xu et al. CORROSION SCIENCE
- Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors
- (2021) Guanyu Jiang et al. JOURNAL OF ALLOYS AND COMPOUNDS
- Improved oxidation and hot corrosion resistance of Ta‐doped NiAlY alloy at 750°C
- (2021) Miao Yu et al. MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
- The influence of Y and Nb addition on the corrosion resistance of Fe-Cr-Al-Ni model alloys exposed to oxygen-containing molten Pb
- (2020) Hao Shi et al. CORROSION SCIENCE
- Enhanced creep resistance of Y-bearing 9Cr ferritic/martensitic steel via vacuum casting technique
- (2019) Yingxue Chen et al. Journal of Materials Research and Technology-JMR&T
- Oxygen concentration measurement and control of lead-bismuth eutectic in a small, static experimental facility
- (2019) Xian Zeng et al. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
- A new method for preparing 9Cr-ODS steel using elemental yttrium and Fe2O3 oxygen carrier
- (2018) Zhiyuan Hong et al. JOURNAL OF ALLOYS AND COMPOUNDS
- Characterization of corrosion phenomena and kinetics on T91 ferritic/martensitic steel exposed at 450 and 550 °C to flowing Pb-Bi eutectic with 10 −7 mass% dissolved oxygen
- (2017) Valentyn Tsisar et al. JOURNAL OF NUCLEAR MATERIALS
- Dissolution corrosion of 316L austenitic stainless steels in contact with static liquid lead-bismuth eutectic (LBE) at 500 °C
- (2017) Konstantina Lambrinou et al. JOURNAL OF NUCLEAR MATERIALS
- Materials Challenges for Generation IV Nuclear Energy Systems
- (2017) T. R. Allen et al. NUCLEAR TECHNOLOGY
- Effect of silicon on the oxidation resistance of 9 wt.% Cr heat resistance steels in 550 °C lead-bismuth eutectic
- (2016) Jian Wang et al. CORROSION SCIENCE
- Dissolution and oxidation behaviour of various austenitic steels and Ni rich alloys in lead-bismuth eutectic at 520 °C
- (2016) Marion Roy et al. JOURNAL OF NUCLEAR MATERIALS
- Low cycle fatigue behavior of a modified 9Cr–1Mo ferritic–martensitic steel in lead–bismuth eutectic at 350°C – Effects of oxygen concentration in the liquid metal and strain rate
- (2015) Xing Gong et al. CORROSION SCIENCE
- Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
- (2015) Y. Yamamoto et al. JOURNAL OF NUCLEAR MATERIALS
- Oxidation behavior of ferritic/martensitic steels in stagnant liquid LBE saturated by oxygen at 600 °C
- (2015) Quanqiang Shi et al. JOURNAL OF NUCLEAR MATERIALS
- Selective leaching of nickel and chromium from Type 316 austenitic steel in oxygen-containing lead–bismuth eutectic (LBE)
- (2014) Carsten Schroer et al. CORROSION SCIENCE
- Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550 °C with 10 −7 mass% dissolved oxygen
- (2014) Valentyn Tsisar et al. JOURNAL OF NUCLEAR MATERIALS
- Lead-Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts
- (2013) Jinsuo Zhang ADVANCED ENGINEERING MATERIALS
- Heavy Liquid Metal Corrosion of Structural Materials in Advanced Nuclear Systems
- (2013) M. Caro et al. JOM
- Corrosion behavior of Si-enriched steels for nuclear applications in liquid lead–bismuth
- (2013) Yuji Kurata JOURNAL OF NUCLEAR MATERIALS
- Corrosion resistance of alloys F91 and Fe–12Cr–2Si in lead–bismuth eutectic up to 715°C
- (2012) M.P. Short et al. JOURNAL OF NUCLEAR MATERIALS
- Selection of fuel cladding material for nuclear fission reactors
- (2011) C.R.F. Azevedo ENGINEERING FAILURE ANALYSIS
- Corrosion behaviour of martensitic and austenitic steels in flowing lead–bismuth eutectic
- (2011) F.J. Martín-Muñoz et al. JOURNAL OF NUCLEAR MATERIALS
- Oxidation kinetics of Y-doped FeCrAl-alloys in low and high pO2 gases
- (2010) D. J. Young et al. MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
- A review of steel corrosion by liquid lead and lead–bismuth
- (2009) Jinsuo Zhang CORROSION SCIENCE
- Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb–Bi melt saturated by oxygen
- (2008) O. Yeliseyeva et al. CORROSION SCIENCE
- Corrosion behavior of steels in liquid lead–bismuth with low oxygen concentrations
- (2007) Yuji Kurata et al. JOURNAL OF NUCLEAR MATERIALS
Find Funding. Review Successful Grants.
Explore over 25,000 new funding opportunities and over 6,000,000 successful grants.
ExploreFind the ideal target journal for your manuscript
Explore over 38,000 international journals covering a vast array of academic fields.
Search