Nickel-free austenitic stainless steel alloys as a sodium-cooled fast reactor fuel cladding-Reference-Cited by-同舟云学术

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Nickel-free austenitic stainless steel alloys as a sodium-cooled fast reactor fuel cladding

Published:2022-09-03 Issue:5 Volume:39 Page:380-386
ISSN:0960-3409
Container-title:Materials at High Temperatures
language:en
Short-container-title:Materials at High Temperatures

Author:

Saeed Aly¹,Mohamed R. H.²,Abu-Raia W. A.³

Affiliation:

1. Mathematical and Natural Sciences Department, Faculty of Engineering, Egyptian-Russian University, Egypt

2. Basic Science Department, Faculty of Engineering, Misr University for Science and Technology, Egypt

3. Basic Science Department, Institute of Aviation Engineering & Technology, Egypt

Publisher

Informa UK Limited

Subject

Materials Chemistry,Metals and Alloys,Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,Ceramics and Composites

Link

https://www.tandfonline.com/doi/pdf/10.1080/09603409.2022.2132041

Reference55 articles.

1. Attenuation capability of low activation-modified high manganese austenitic stainless steel for fusion reactor system

2. Development of cladding materials for sodium-cooled fast reactors in India

3. Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors

4. High Temperature Materials for Nuclear Fast Fission and Fusion Reactors and Advanced Fossil Power Plants

5. Properties of Austenitic Steels for Nuclear Reactor Applications

Cited by 3 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. High ductility – Good strength stainless steel alloys at the elevated temperature for nuclear reactors core;Progress in Nuclear Energy;2024-02

2. Microstructure Features and Mechanical Properties of Modified Low-Activation Austenitic Steel in the Temperature Range of 20 to 750 °C;Metals;2023-12-15

3. Developed borated austenitic stainless steel alloys as nuclear reactor control rods;Nuclear Engineering and Design;2023-11

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