Austenitic stainless steel for core structural members of light water reactors

• 1. 核电站反应堆的堆内构件用奥氏体不锈钢锻件的锻造方法 [P] . 中国专利： CN102828009A . 2012-12-19
• 2. 快中子反应堆用奥氏体不锈钢钢板及其制造方法 [P] . 中国专利： CN113564461A . 2021-10-29
• 3. Austenitic stainless steel, particularly usable as a core structural or canning material in nuclear reactors [P] . 美国专利： US4778651A . 1988-10-18

  机译： 奥氏体不锈钢，尤其可用作核反应堆的核心结构或罐头材料

• 4. Austenitic stainless steel particularly suitable as a structural core material or as a cladding material in nuclear reactors [P] . 欧洲知识产权局专利： EP0233426A1 . 1987-08-26

  机译： 奥氏体不锈钢，特别适合用作核反应堆的结构核心材料或包覆材料

• 5. AUSTENITIC STAINLESS STEEL USED AS STRUCTURAL MATERIAL FOR CORE OR FAST BREEDER REACTOR [P] . 日本专利： JPS6187853A . 1986-05-06

  机译： 奥氏体不锈钢用作核心或快速育种机的结构材料

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• 2. Measurement of the Deformability of Austenitic Stainless Steels and Nickel-Base Alloys in Light Water Reactor Cores [C] . P. Dewes, D. Alter, F. Garzarolli, Slow strain rate testing for the evaluation of environmentally induced cracking: Research and engineering applications . 1993
• 3. High Temperature Creep-Fatigue Behavior of Alloy 709 Austenitic Stainless Steel in Sodium-Cooled Fast Reactors [D] . Alsmadi, Zeinab Yousef. 2020
• 4. Structural Transformations in Austenitic Stainless Steel Induced by Deuterium Implantation: Irradiation at 295 K [O] . Oleksandr Morozov, Volodymir Zhurba, Ivan Neklyudov, 2016
• 5. Slow strain rate tensile tests on irradiated austenitic stainless steels in simulated light water reactor environments [O] . Y. Chen, A.S. Rao, B. Alexandreanu, 2014
• 6. Evaluation of Welded and Repair-Welded Stainless Steel for Light Water Reactor (LWR) Service: Compositional Effects on the Sensitization of Austenitic Stainless Steels. [R] . Bruemmer, S. M., Charlot, L. A., Atteridge, D. G. 1984

• 1. Effect of cold rolling on the microstructural,magnetic,mechanical,and corrosion properties of AISI 316L austenitic stainless steel [J] . S. Tanhaei ,Kh. Gheisari ,S.R. Alavi Zaree . 矿物冶金与材料学报 . 2018,第006期
• 2. Microstructural evolution and mechanical properties of friction stir-welded C71000 copper–nickel alloy and 304 austenitic stainless steel [J] . Hamed Jamshidi Aval . 矿物冶金与材料学报 . 2018,第011期
• 3. Microstructural evolution and mechanical properties of aging high nitrogen austenitic stainless steels [J] . Zhou-hua Jiang ,Zu-rui Zhang ,Hua-bing Li . 矿物冶金与材料学报 . 2010,第006期
• 4. Microstructural evolution and mechanical properties of aging high nitrogen austenitic stainless steels [J] . Zhou-hua Jiang ,Zu-rui Zhang ,Hua-bing Li . 矿物冶金与材料学报 . 2010,第006期
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