Tensile and Charpy impact properties of reduced activation ferritic/martensitic steel with small amounts of Ta and Ti-Reference-Cited by-同舟云学术

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Tensile and Charpy impact properties of reduced activation ferritic/martensitic steel with small amounts of Ta and Ti

Published:2020-01 Issue: Volume:528 Page:151862
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Choi Jin-Young,Moon Joonoh,Kim Byung Hwan,Jang Jae Hoon,Lee Tae-Ho,Hong Hyun-Uk,Kim Hyoung Chan,Lee Chang-Hoon,Kang Nam Hyun

Funder

Korea Institute of Materials Science

Publisher

Elsevier BV

Subject

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

Reference24 articles.

1. Ferritic/martensitic steels – overview of recent results

2. Overview of materials research for fusion reactors

3. Present limits and improvements of structural materials for fusion reactors – a review

4. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket

5. Microstructural evolution and mechanical performances of SiC/SiC composites by polymer impregnation/microwave pyrolysis (PIMP) process

Cited by 10 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. Mechanical and helium swelling responses of K-RAFM steels to Fe ion irradiation and helium implantation;Nuclear Materials and Energy;2024-06

2. Micro-alloying effects of Ta and B on nano-oxides and grain boundaries in 13CrWTi-ODS ferritic alloys;Journal of Alloys and Compounds;2024-01

3. Improving thermal conductivity of reduced-activation ferritic/martensitic steel using three-dimensional woven copper fiber;Fusion Engineering and Design;2023-12

4. Influence of Ti addition on MX precipitation and creep-fatigue properties of RAFM steel for nuclear fusion reactor;Journal of Nuclear Materials;2022-12

5. Influence of W concentration on the Charpy impact property and corrosion behavior of reduced activation ferritic-martensitic steels for fusion reactor;Journal of Nuclear Materials;2022-10

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