The void swelling behavior of heavy ion irradiated D9 steel has been investigated using variable low energy positron beam. The normalized defect-sensitive S-parameter shows up a large increase in the depth region corresponding to the maximum radiation damage as a function of irradiation temperature. From the variation of S-parameter as a function of irradiation temperature, the peak swelling temperature has been deduced and the results are discussed
The microstructures, irradiation-induced defects and changes of mechanical property of Chinese domes...
Large amounts of void swelling still limit the application of austenitic stainless steels in nuclear...
An investigation of a commercial oxide dispersion-strengthened steel (MA9561) irradiated with high e...
The void swelling behaviour of (15Ni-14Cr) Ti-modified steels simulated by heavy ion irradiation, ha...
The void swelling behavior of D9 with 0.25Ti and D9 with 0.15Ti modified steels was studied using he...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
In this work the void swelling behavior of a 9Cr ferritic/martensitic steel irradiated with energeti...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
Specimens of 15Kh2MFAA steel used for reactor pressure vessels V-213 (VVER-440 reactor) were studied...
The defect recovery in proton irradiated Ti-modified D9 steel has been studied by positron annihilat...
Positron annihilation studies on austentic and ferritic/martensitic and oxide-dispersion steels are ...
Ferritic/martensitic alloys are required for advanced reactor components to survive 500-600 neutron-...
The microstructures, irradiation-induced defects and changes of mechanical property of Chinese domes...
Large amounts of void swelling still limit the application of austenitic stainless steels in nuclear...
An investigation of a commercial oxide dispersion-strengthened steel (MA9561) irradiated with high e...
The void swelling behaviour of (15Ni-14Cr) Ti-modified steels simulated by heavy ion irradiation, ha...
The void swelling behavior of D9 with 0.25Ti and D9 with 0.15Ti modified steels was studied using he...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
In this work the void swelling behavior of a 9Cr ferritic/martensitic steel irradiated with energeti...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
To understand the role of different metallurgical parameters on the void formation mechanisms, vario...
Specimens of 15Kh2MFAA steel used for reactor pressure vessels V-213 (VVER-440 reactor) were studied...
The defect recovery in proton irradiated Ti-modified D9 steel has been studied by positron annihilat...
Positron annihilation studies on austentic and ferritic/martensitic and oxide-dispersion steels are ...
Ferritic/martensitic alloys are required for advanced reactor components to survive 500-600 neutron-...
The microstructures, irradiation-induced defects and changes of mechanical property of Chinese domes...
Large amounts of void swelling still limit the application of austenitic stainless steels in nuclear...
An investigation of a commercial oxide dispersion-strengthened steel (MA9561) irradiated with high e...