Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for SCWR in superheated steam-Reference-Cited by-同舟云学术

Oxidation behavior of austenitic stainless steels as fuel cladding candidate materials for SCWR in superheated steam

Published:2014-12 Issue: Volume:280 Page:652-660
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Abe Hiroshi,Hong Seung Mo,Watanabe Yutaka

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference29 articles.

1. The effect of grain size on the corrosion behavior of INCONEL 600 in high-temperature steam;Abe;Corros. Sci.,1981

2. Materials challenges for Generation IV nuclear energy systems;Allen;Nucl. Technol.,2008

3. Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water;Ampornrat;J. Nucl. Mater.,2007

4. Corrosion behavior of ferritic–martensitic steel T91 in supercritical water;Chen;Corros. Sci.,2006

5. Study of parabolic constant for coated AISI 430 steel with Mn3O4 and MnFe2O4 spinels;Ebrahimifar;Indian J. Eng. Mater. Sci.,2011

Cited by 15 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

1. TEM comparative study on oxide films of 316L and T91 steel exposed to 350–500 °C steam;Journal of Materials Science & Technology;2024-03

2. Flow instability in parallel-channel systems with ultra-supercritical water;International Communications in Heat and Mass Transfer;2020-12

3. Oxidation behavior analysis of a ferritic ODS steel in supercritical Water;Fusion Engineering and Design;2020-12

4. Preparation and Characterization of Slurry Aluminide Coating on TP347H FG Stainless Steel;Metallurgical and Materials Transactions A;2019-05-29

5. Thermomechanical processing of advanced high strength steels;Progress in Materials Science;2018-05