Synergistic Effects in Reduced-Activation Martensitic Steel Under Single and Sequential Helium/Hydrogen Ion Irradiation

2014 ◽  
Vol 66 (2) ◽  
pp. 301-307 ◽  
Author(s):  
Jihong Chen ◽  
Liping Guo ◽  
Fengfeng Luo ◽  
Tiecheng Li ◽  
Yaoyao Ren ◽  
...  
Keyword(s):  
Martensitic Steel ◽  
Ion Irradiation ◽  
Synergistic Effects ◽  
Hydrogen Ion

Anisotropy dispersion in the exchange-biased pinned layer of a spin valve prepared by 550 eV hydrogen-ion irradiation

2009 ◽  
Vol 105 (7) ◽  
pp. 07D719 ◽  
Author(s):  
Soogil Lee ◽  
Yoonsung Han ◽  
Sanghoon Kim ◽  
Jongill Hong
Keyword(s):  
Ion Irradiation ◽  
Spin Valve ◽  
Hydrogen Ion

Study of Nanostructure of Ferritic-Martensitic Steel ChS-139 in Initial State and after Fe Ion Irradiation

2018 ◽  
Vol 9 (2) ◽  
pp. 231-238 ◽  
Author(s):  
S. V. Rogozhkin ◽  
N. A. Iskandarov ◽  
A. A. Lukyanchuk ◽  
A. S. Shutov ◽  
O. A. Raznitsyn ◽  
...  
Keyword(s):  
Martensitic Steel ◽  
Ion Irradiation ◽  
Initial State

Microstructural evolution of P92 ferritic/martensitic steel under Ar+ ion irradiation at elevated temperature

2012 ◽  
Vol 68 ◽  
pp. 63-70 ◽  
Author(s):  
Shuoxue Jin ◽  
Liping Guo ◽  
Tiecheng Li ◽  
Jihong Chen ◽  
Zheng Yang ◽  
...  
Keyword(s):  
Elevated Temperature ◽  
Microstructural Evolution ◽  
Martensitic Steel ◽  
Ion Irradiation

In Situ TEM Observation of Precipitation of Zirconium Hydrides in Zircaloy-4 under Hydrogen Ion Implantation

2007 ◽  
Vol 561-565 ◽  
pp. 1765-1768 ◽  
Author(s):  
Yasunari Shinohara ◽  
Hiroaki Abe ◽  
Toshiya Kido ◽  
Takeo Iwai ◽  
Naoto Sekimura
Keyword(s):  
Nuclear Fuel ◽  
Ion Irradiation ◽  
Hydrogen Ion ◽  
Zirconium Hydride ◽  
Precipitation Process ◽  
In Situ Tem ◽  
Fuel Cladding ◽  
Hydrogen Implantation ◽  
Nuclear Fuel Cladding ◽  
Zirconium Hydrides

The formation of hydrides in zirconium alloy has been one of the essential matters of discussion to maintain mechanical strength of nuclear fuel cladding tubes. In this work, we examined the precipitation process of zirconium hydride by transmission electron microscopy under hydrogen ion irradiation. Zircaloy-4, which has been used extensively as nuclear fuel cladding, was irradiated with hydrogen ion at room temperature to achieve enough hydrogen concentration for precipitation. The growth of hydrides accompanied with dislocations around hydrides was observed under hydrogen implantation. The observed hydride was the γ-hydride phase with fct structure and the orientation relationship was <110>γ ||<1120>α as reported previously. As the hydride grew, the dislocations were generated gradually. This process can be explained using a ratchet mechanism suggested by Carpenter. The growth rate became lower according to the approach of other hydrides. This behavior is considered to be influenced by the strain field caused by other hydrides.

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