Long-term thermal-aging stability of oxide-dispersion-strengthened ferritic steels at 753 K

2018 ◽  
Vol 25 (7) ◽  
pp. 776-784
Author(s):  
Shuai Xu ◽  
Zhang-jian Zhou ◽  
Shao-fu Li ◽  
Hao-dong Jia
Keyword(s):  
Thermal Aging ◽  
Oxide Dispersion Strengthened ◽  
Ferritic Steels ◽  
Oxide Dispersion

Long-term thermal-aging stability of a 16Cr-oxide dispersion strengthened ferritic steel at 973 K

2016 ◽  
Vol 90 ◽  
pp. 318-329 ◽  
Author(s):  
S.F. Li ◽  
Z.J. Zhou ◽  
P.H. Wang ◽  
H.Y. Sun ◽  
M. Wang ◽  
...  
Keyword(s):  
Thermal Aging ◽  
Ferritic Steel ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion

Effect of Pulsed Fluxes of Deuterium Ions and Deuterium Plasma on Oxide Dispersion Strengthened Ferritic Steels

2021 ◽  
Vol 12 (3) ◽  
pp. 601-609
Author(s):  
V. A. Gribkov ◽  
E. V. Demina ◽  
A. S. Demin ◽  
S. A. Maslyaev ◽  
V. N. Pimenov ◽  
...  
Keyword(s):  
Oxide Dispersion Strengthened ◽  
Ferritic Steels ◽  
Oxide Dispersion ◽  
Deuterium Plasma

Effects of Neutron Irradiation and Thermal Aging on Mechanical Properties of ODS Ferritic Steels for Advanced Nuclear Systems

2007 ◽  
Vol 561-565 ◽  
pp. 1773-1776 ◽  
Author(s):  
Ryuta Kasada ◽  
Hang Sik Cho ◽  
Naoyuki Okuda ◽  
Akihiko Kimura
Keyword(s):  
Neutron Irradiation ◽  
Thermal Aging ◽  
Charpy Impact ◽  
Oxide Dispersion Strengthened ◽  
Tensile Tests ◽  
Total Elongation ◽  
Ferritic Steels ◽  
Dislocation Loops ◽  
Irradiation Hardening ◽  
Nuclear Systems

Effects of neutron irradiation and thermal aging on the tensile properties and Charpy impact properties of oxide dispersion strengthened (ODS) ferritic steels for advanced nuclear systems were investigated and discussed with the results of microstructural observation. After the neutron irradiation in JMTR, significant hardening after irradiation at 290 and 400 °C as well as thermal aging at 500 °C, while no effect was observed after irradiation at 600 °C. While the irradiation hardening was not accompanied by a reduction of total elongation in tensile tests, Charpy impact energy at room temperature was reduced after the irradiation. The hardening after the irradiation at 400 °C and the aging at 500 °C was probably due to the formation of Cr-rich phases. The irradiation hardening observed in the ODS ferritic steels irradiated at 290 °C was well explained by the formation of dislocation loops.

Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels

2004 ◽  
Vol 335 (3) ◽  
pp. 311-321 ◽  
Author(s):  
I. Monnet ◽  
P. Dubuisson ◽  
Y. Serruys ◽  
M.O. Ruault ◽  
O. Kaı¨tasov ◽  
...  
Keyword(s):  
Oxide Dispersion Strengthened ◽  
Ferritic Steels ◽  
Oxide Dispersion ◽  
Microstructural Investigation ◽  
The Stability

Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I)

1997 ◽  
Vol 34 (3) ◽  
pp. 256-263 ◽  
Author(s):  
Shigeharu UKAI ◽  
Toshio NISHIDA ◽  
Hirokazu OKADA ◽  
Takanari OKUDA ◽  
Masayuki FUJIWARA ◽  
...  
Keyword(s):  
Oxide Dispersion Strengthened ◽  
Ferritic Steels ◽  
Oxide Dispersion
Sign in / Sign up

Export Citation Format

Share Document