Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Zhen-feng TONG"'
Microstructure and mechanical properties of 15Ni‒15Cr oxide dispersion strengthened austenitic steel
Publikováno v:
工程科学学报, Vol 45, Iss 1, Pp 107-116 (2023)
The development of advanced cladding material with improved service performance is a key issue in engineering applications of sodium-cooled fast reactors. At present, the cladding materials of sodium-cooled fast reactors are mainly AISI type 316 or 1
Externí odkaz:
https://doaj.org/article/77207128dd564edabda0dbcd7e8afc0b
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 329:1277-1290
Pyrolytic biochar and hydrothermal biochar of corn stalk were prepared at different temperatures, and their abilities to remove iodate were compared. The characterization results show that the preparation temperature determines the degree of carboniz
Publikováno v:
Nuclear Engineering and Design. 392:111765
Fatigue Mechanism of Domestic 316LN Stainless Steel in Simulated AP1000 First-Loop Water Environment
Publikováno v:
Materials Science Forum. 913:247-253
Fatigue fracture surfaces and crack morphologies of 316LN stainless steel that test in a simulated AP1000 first-loop water and air environment were investigated by SEM, LSCM and EBSD. The results showed that, the fatigue crack initiated at persistent
Publikováno v:
Materials Science Forum. 850:41-46
Reactor pressurized vessel (RPV), which determines the lifetime of the nuclear power plant (NPP), is mainly forged using A508-3 steel in China. In order to meet the requirement of the small specimen test technique in the nuclear application, the frac
Publikováno v:
Materials Science Forum. 850:96-100
In this work, impact toughness and tensile properties of valve stem used in NPP are obtained. Combining with microstructure analysis of fracture morphology and metallurgical structure, the thermal aging behavior of the martensitic stainless steel is