On the thermal stability of a 9Cr-ODS steel aged at 700 °C up to 10000 h - Mechanical properties and microstructure-Reference-Cited by-同舟云学术

On the thermal stability of a 9Cr-ODS steel aged at 700 °C up to 10000 h - Mechanical properties and microstructure

Published:2020-05 Issue: Volume:783 Page:139292
ISSN:0921-5093
Container-title:Materials Science and Engineering: A
language:en
Short-container-title:Materials Science and Engineering: A

Author:

Zheng Pengfei,Li Yanfen,Zhang Jiarong,Shen Jingjie,Nagasaka Takuya,Muroga Takeo,Abe Hiroaki

Funder

National Nature Science Foundation of China

Institute of Metal Research Chinese Academy of Science

Japan Society for the Promotion of Science

National Institute for Fusion Science

The University of Tokyo in Japan

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Reference28 articles.

1. On the status and prospects for nanostructured ferritic alloys for nuclear fission and fusion application with emphasis on the underlying science;Robert Odette;Scripta Mater.,2018

2. A review of refractory metal alloys and mechanically alloyed-oxide dispersion strengthened steels for space nuclear power systems;El-Genk;J. Nucl. Mater.,2005

3. Oxide Dispersion-Strengthened/ferrite-Martensite Steels as Core Materials for Generation IV Nuclear Reactors, Structural Materials for Generation IV Nuclear Reactors;Ukai,2017

4. Fabrication and characterization of reference 9Cr and 12Cr-ODS low activation ferritic/martensitic steels;Muroga;Fusion Eng. Des.,2014

5. Review on the EFDA work programme on nano-structured ODS RAF steels;Baluc;J. Nucl. Mater.,2011

Cited by 27 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. Multi-objective optimization assisting three-dimensional quantitative Cahn-Hilliard simulations of microstructure evolution in Fe-Cr alloys during spinodal decomposition;Computational Materials Science;2024-09

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

3. Secondary phases characterization by SANS and XAS of an ODS ferritic steel after thermal aging at 873 K;Nuclear Materials and Energy;2024-06

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

5. Revealing the temperature-dependent hardening mechanisms of non-uniformly distributed defects for ion-irradiated metals: Experiments and modeling;Materials Science and Engineering: A;2024-05