Study on anisotropy in microstructure and tensile properties of the 12Cr oxide dispersion strengthened (ODS) steel-Reference-Cited by-同舟云学术

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Study on anisotropy in microstructure and tensile properties of the 12Cr oxide dispersion strengthened (ODS) steel

Published:2019-09 Issue: Volume:146 Page:1082-1085
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Shen Jingjie,Nagasaka Takuya,Muroga Takeo,Li Yanfen,Yang Huilong,Kano Sho,Abe Hiroaki

Funder

National Institute for Fusion Science Collaboration Research program

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference25 articles.

1. R&D of oxide dispersion strengthened ferritic martensitic steels for FBR;Ukai;J. Nucl. Mater.,1998

2. Development of an oxide dispersion strengthened, reduced-activation steel for fusion energy;Romanoski;J. Nucl. Mater.,2000

3. Perspective of ODS alloys application in nuclear environments;Ukai;J. Nucl. Mater.,2002

4. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials;Ukai;J. Nucl. Mater.,1993

5. Oxide dispersion-strengthened steels: a comparison of some commercial and experimental alloys;Klueh;J. Nucl. Mater.,2005

Cited by 5 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. In-Situ synchrotron investigation of elastic and tensile properties of oxide dispersion strengthened EUROFER97 steel for advanced fusion reactors;Acta Materialia;2024-06

2. Anisotropic effects of radiation-induced hardening in nuclear structural materials: A review;Journal of Nuclear Materials;2022-04

3. Effect of Plastic Anisotropy on the Kinetics of Static Softening in AA2024–T3 Aluminum Alloy;Metals and Materials International;2022-02-04

4. Hardening behavior and deformation microstructure beneath indentation in heavy ion irradiated 12Cr-ODS steel at elevated temperature;Journal of Nuclear Materials;2021-01

5. Investigation of anisotropic hardening response in a 12Cr-ODS ferritic steel subjected to 2.8 MeV Fe2+ irradiation;Journal of Nuclear Materials;2020-04

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