Characterization of oxide particles in ODS austenitic stainless steel after heavy ion irradiation up to high doses

2011 ◽  
Vol 1298 ◽  
Author(s):  
Hiroshi Oka ◽  
Yosuke Yamazaki ◽  
Hiroshi Kinoshita ◽  
Naoyuki Hashimoto ◽  
Somei Ohnuki ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Hot Extrusion ◽  
Oxide Dispersion Strengthened ◽  
Complex Oxide ◽  
Heavy Ion ◽  
Oxide Particles ◽  
The Difference ◽  
High Doses

ABSTRACTOxide dispersion strengthened austenitic stainless steel (ODS316), which is based on advanced SUS316 steel, has been developed by mechanically alloying and hot extrusion. Hafnium and titanium were added to make a fine distribution of oxide particles. The stability of oxide particles dispersed in ODS316 under irradiation was evaluated after 250 keV Fe+ irradiation up to high doses at 500 °C. TEM observation and EDS analysis indicated that fine complex oxide particles with Y, Hf and Ti were mainly dispersed in the matrix. There are no significant changes in the distribution and the size of oxide particles after irradiation. It was also revealed that the constitution ratio of Ti in complex oxide appeared to be decreased after irradiation. This diffuse-out of Ti during irradiation could be explained by the difference in oxide formation energy among alloying elements.

scholarly journals In situ TEM study of G-phase precipitates under heavy ion irradiation in CF8 cast austenitic stainless steel

2015 ◽  
Vol 464 ◽  
pp. 185-192 ◽  
Author(s):  
Wei-Ying Chen ◽  
Meimei Li ◽  
Xuan Zhang ◽  
Marquis A. Kirk ◽  
Peter M. Baldo ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
In Situ Tem ◽  
Heavy Ion Irradiation

scholarly journals Effect of heavy ion irradiation on microstructural evolution in CF8 cast austenitic stainless steel

2016 ◽  
Vol 471 ◽  
pp. 184-192 ◽  
Author(s):  
Wei-Ying Chen ◽  
Meimei Li ◽  
Marquis A. Kirk ◽  
Peter M. Baldo ◽  
Tiangan Lian
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Microstructural Evolution ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
Heavy Ion Irradiation

scholarly journals Thermodynamics of an austenitic stainless steel (AISI-348) under in situ TEM heavy ion irradiation

2019 ◽  
Vol 179 ◽  
pp. 360-371 ◽  
Author(s):  
Matheus A. Tunes ◽  
Graeme Greaves ◽  
Thomas M. Kremmer ◽  
Vladimir M. Vishnyakov ◽  
Philip D. Edmondson ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
In Situ Tem ◽  
Heavy Ion Irradiation ◽  
Steel Aisi ◽  
Stainless Steel Aisi

Mechanical and Microstructural Properties of Al-Added ODS Ferritic Steel

2012 ◽  
Vol 567 ◽  
pp. 49-53 ◽  
Author(s):  
Jae Hoon Lee
Keyword(s):  
Hot Extrusion ◽  
Oxide Dispersion Strengthened ◽  
Tensile Tests ◽  
Ods Steel ◽  
Dispersed Particles ◽  
Oxide Particles ◽  
Ods Steels ◽  
Ductile To Brittle Transition ◽  
The Difference ◽  
Mechanical And Microstructural Properties

18%Cr-oxide dispersion strengthened (ODS) ferritic steels with and without 5%Al have been produced by mechanical alloying and hot-extrusion. The microstructure of the ODS steels has been characterized by means of electron microscopy (SEM, TEM), showing that in the Al-added ODS steel, the semi-coherent and coherent oxide particles are about 75% and 10%, respectively. It was found that the coherency of oxide particles depends on the size of dispersed particles. Tensile tests performed between room temperature and 973 K denote that the ultimate tensile strength of Al-free ODS steel is higher than that of Al-added one. The ductility values of both materials are sufficiently high. Impact tests reveal that the ductile-to-brittle transition temperature of Al-free ODS steel are higher than that of Al-added ODS steel; however, the upper shelf energy of 18%Cr-ODS steel is substantially smaller in comparison to the Al-added one. It is considered that the difference in mechanical properties between Al-free and Al-added ODS steels is caused by the smaller, stable titania + yttria complex oxides dispersed in the Al-free ODS steel.

scholarly journals Heavy ion irradiation response of an additively manufactured 316LN stainless steel

2020 ◽  
pp. 152745
Author(s):  
Zhongxia Shang ◽  
Cuncai Fan ◽  
Jie Ding ◽  
Sichuang Xue ◽  
Adam Gabriel ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
316Ln Stainless Steel ◽  
Heavy Ion Irradiation

Nucleation and amorphization of radiation-produced phases in a modified austenitic stainless steel during Ni-ion irradiation

1988 ◽  
Vol 3 (5) ◽  
pp. 840-844 ◽  
Author(s):  
E. H. Lee ◽  
E. A. Kenik
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Amorphous State ◽  
Dislocation Loops ◽  
Nickel Ion ◽  
Carbide Phases ◽  
Direct Formation ◽  
Radiation Induced ◽  
Lower Temperature

The nucleation and amorphization of radiation-induced (G) and radiation-enhanced (η) phases in a silicon- and titanium-modified austenitic stainless steel have been studied under nickel-ion irradiation. These silicon- and nickel-enriched phases form under high-temperature (950 K) irradiation as the result of radiation-induced segregation to radiation-produced interstitial dislocation loops. Availability of carbon promotes the formation of η phase relative to G phase. Under lower temperature (450 K) irradiation, G and η phases are amorphized without significant change in composition of metallic elements. Two carbide phases (MC, M23C6) remain crystalline for the same irradiation conditions. The amorphization of the silicides may result from (1) radiation damage increasing their free energy above that of the amorphous state or (2) direct formation of the amorphous phase in the damage cascade.

Corrosion behavior of a 304-oxide dispersion strengthened austenitic stainless steel in supercritical water

2015 ◽  
Vol 67 (3) ◽  
pp. 264-270 ◽  
Author(s):  
S. F. Li ◽  
Z. J. Zhou ◽  
L. F. Zhang ◽  
L. W. Zhang ◽  
H. L. Hu ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Corrosion Behavior ◽  
Supercritical Water ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion

Argon-ion irradiation erosion of a 316 austenitic stainless steel

1986 ◽  
Vol 5 (9) ◽  
pp. 843-844
Author(s):  
T. Yamane ◽  
N. Hiramatsu ◽  
K. Hirao ◽  
A. Arata
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Ion Irradiation ◽  
Argon Ion
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