Hardening behavior and deformation microstructure beneath indentation in heavy ion irradiated 12Cr-ODS steel at elevated temperature

2021 ◽  
Vol 543 ◽  
pp. 152606
Author(s):  
H.L. Yang ◽  
S. Kano ◽  
J. McGrady ◽  
J.J. Shen ◽  
Y.F. Li ◽  
...  
Keyword(s):  
Elevated Temperature ◽  
Heavy Ion ◽  
Deformation Microstructure ◽  
Hardening Behavior ◽  
Ods Steel

Hardening behavior of three metallic alloys under combined stresses at elevated temperature

2004 ◽  
Vol 169 (1-4) ◽  
pp. 53-77 ◽  
Author(s):  
C. J. Lissenden ◽  
J. F. Colaiuta ◽  
B. A. Lerch
Keyword(s):  
Elevated Temperature ◽  
Metallic Alloys ◽  
Hardening Behavior ◽  
Combined Stresses

Irradiation damage and swelling of carbon-doped Fe38Mn40Ni11Al4Cr7 high-entropy alloys under heavy ion irradiation at elevated temperature

2020 ◽  
Vol 55 (36) ◽  
pp. 17218-17231
Author(s):  
Shangkun Shen ◽  
Feida Chen ◽  
Xiaobin Tang ◽  
Guojia Ge ◽  
Jing Gao ◽  
...  
Keyword(s):  
Elevated Temperature ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
Irradiation Damage ◽  
High Entropy Alloys ◽  
High Entropy ◽  
Carbon Doped ◽  
Heavy Ion Irradiation

scholarly journals Inelastic Material Models of Type 316H for Elevated Temperature Design of Advanced High Temperature Reactors

Energies ◽  
2020 ◽  
Vol 13 (17) ◽  
pp. 4548
Author(s):  
Gyeong-Hoi Koo ◽  
Ji-Hyun Yoon
Keyword(s):  
High Temperature ◽  
Elevated Temperature ◽  
Constitutive Equations ◽  
Isotropic Hardening ◽  
Material Models ◽  
Material Parameters ◽  
Hardening Behavior ◽  
Inelastic Material ◽  
High Temperature Reactors ◽  
Elevated Temperature Design

In this paper, the inelastic material models for Type 316H stainless steel, which is one of the principal candidate materials for elevated temperature design of the advanced high temperature reactors (HTRs) pressure retained components, are investigated and the required material parameters are identified to be used for both elasto-plastic models and unified viscoplastic models. In the constitutive equations of the inelastic material models, the kinematic hardening behavior is expressed with the Chaboche model with three backstresses, and the isotropic hardening behavior is expressed by the Voce model. The required number of material parameters is minimized to be ten in total. For the unified viscoplastic model, which can express both the time-independent plastic behavior and the time-dependent viscous behavior, the constitutive equations have the same kinematic and isotropic hardening parameters of the elasto-plastic material model with two additional viscous parameters. To identify the material parameters required for these constitutive equations, various uniaxial tests were carried out at isothermal conditions at room temperature and an elevated temperature range of 425–650 °C. The identified inelastic material parameters were validated through the comparison between tests and calculations.

Elevated-temperature heavy-ion damage in (Co0.78Fe0.22)3V ordered alloy

1985 ◽  
Vol 136 (1) ◽  
pp. 48-58 ◽  
Author(s):  
D.M. Braski ◽  
K. Farrell
Keyword(s):  
Elevated Temperature ◽  
Heavy Ion ◽  
Ion Damage

Sodium compatibility of ODS steel at elevated temperature

2004 ◽  
Vol 329-333 ◽  
pp. 1393-1397 ◽  
Author(s):  
Eiichi Yoshida ◽  
Shoichi Kato
Keyword(s):  
Elevated Temperature ◽  
Ods Steel

Microstructural stability of an as-fabricated 12Cr-ODS steel under elevated-temperature annealing

2017 ◽  
Vol 695 ◽  
pp. 1946-1955 ◽  
Author(s):  
Jingjie Shen ◽  
Huilong Yang ◽  
Yanfen Li ◽  
Sho Kano ◽  
Yoshitaka Matsukawa ◽  
...  
Keyword(s):  
Elevated Temperature ◽  
Microstructural Stability ◽  
Ods Steel

Irradiation Hardening in Ferritic/Martensitic Steel P92 during Ar-Ions Irradiation at Elevated Temperature

2013 ◽  
Vol 378 ◽  
pp. 289-292 ◽  
Author(s):  
Jun Zhu ◽  
Yin Zhong Shen
Keyword(s):  
Elevated Temperature ◽  
Martensitic Steel ◽  
Martensitic Steels ◽  
Irradiation Hardening ◽  
Hardening Behavior ◽  
First Time

The irradiation hardening behavior in a commercial ferritic/martensitic steel P92 has been investigated through 250KeV Ar-ions irradiations to a dose of 10dpa at 473, 673 and 973K combined with nanoindentation techniques. The results show that irradiation-induced hardening was observed at the all irradiation temperatures. There appear to have no previous reports of the irradiation-induced hardening at the temperature higher than 873K in ferritic/martensitic steels. Irradiation-induced hardening at elevated temperature of 973K has been found, for the first time, in ferritic/martensitic steel. The irradiation-induced hardening at 973K in the ferritic/martensitic steel P92 may be ascribed to the defects in the steel generated by Ar-ions irradiation.

scholarly journals Positron annihilation study of the hardening behavior in Al-Cu based alloy by electron and heavy ion irradiation

2010 ◽  
Vol 225 ◽  
pp. 012014
Author(s):  
Fuminobu Hori ◽  
Ippei Kobayashi ◽  
Yuichi Saito ◽  
Norito Ishikawa ◽  
Takeshi Oshima ◽  
...  
Keyword(s):  
Positron Annihilation ◽  
Ion Irradiation ◽  
Heavy Ion ◽  
Hardening Behavior ◽  
Heavy Ion Irradiation ◽  
Positron Annihilation Study

Swift heavy ion tracks in Y2Ti2O7 nanoparticles in EP450 ODS steel

2015 ◽  
Vol 456 ◽  
pp. 111-114 ◽  
Author(s):  
V.A. Skuratov ◽  
A.S. Sohatsky ◽  
J.H. O’Connell ◽  
K. Kornieieva ◽  
A.A. Nikitina ◽  
...  
Keyword(s):  
Heavy Ion ◽  
Ion Tracks ◽  
Ods Steel ◽  
Swift Heavy Ion
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