Corrosion behavior of Al-alloying high Cr-ODS steels in lead–bismuth eutectic-Reference-Cited by-同舟云学术

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Corrosion behavior of Al-alloying high Cr-ODS steels in lead–bismuth eutectic

Published:2009-04 Issue: Volume:386-388 Page:507-510
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Takaya S.,Furukawa T.,Aoto K.,Müller G.,Weisenburger A.,Heinzel A.,Inoue M.,Okuda T.,Abe F.,Ohnuki S.,Fujisawa T.,Kimura A.

Publisher

Elsevier BV

Subject

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

Reference9 articles.

1. Corrosion of stainless steels in lead–bismuth eutectic up to 600 °C

2. Behavior of steels in flowing liquid PbBi eutectic alloy at 420–600 °C after 4000–7200 h

3. Compatibility tests on steels in molten lead and lead–bismuth

4. Investigation on oxygen controlled liquid lead corrosion of surface treated steels

5. Results of steel corrosion tests in flowing liquid Pb/Bi at 420–600 °C after 2000 h

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1. Chemical states of corrosion products in liquid lead from ab initio molecular dynamics;Journal of Nuclear Materials;2024-10

2. Early corrosion behavior of low carbon 9Cr-ODS steel in high temperature oxygen-saturated lead-bismuth eutectic;Corrosion Science;2024-08

3. The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review;Materials;2024-07-10

4. The Effects of Irradiation on the Improvement in Oxidation Behavior of MX-ODS Steel in Liquid Pb;Nanomaterials;2024-05-04

5. Effect of post-annealing on the oxidation behavior of hot rolled ODS-FeCrAl steel in liquid lead;Corrosion Science;2024-03

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