High-temperature creep and corrosion behavior of 316LN stainless steel in oxygen-saturated sodium
Author:
Funder
Science Fund for Distinguished Young Scholars of Hebei Province
National Natural Science Foundation of China
Publisher
Elsevier BV
Reference36 articles.
1. A summary of sodium-cooled fast reactor development;Aoto;Prog. Nucl. Energy.,2014
2. Evaluation procedures for irradiation effects and sodium environmental effects for the structural design of Japanese fast breeder reactors;Asayama;J. Pressure Vessel Technol.,2001
3. Effect of flowing sodium on corrosion and tensile properties of AISI type 316LN stainless steel at 823 K;Barasi;J. Nucl. Mater.,2008
4. Evaluation of microstructural, mechanical properties and corrosion behavior of AISI type 316LN stainless steel and modified 9Cr-1Mo steel exposed in a dynamic bimetallic sodium loop at 798 K (525 °C) for 16,000 hours;Barasi;Metall. Mater. Trans. a.,2012
5. Changes in microstructural and mechanical properties of AISI type 316LN stainless steel and modified 9Cr-1Mo steel on long-term exposure to flowing sodium in a bi-metallic sodium loop;Barasi;Metall. Mater. Trans. a.,2015
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