Add to ORKGThe long term mechanical integrity of the pipes used to carry the primary cooling water in a pressurized water nuclear reactor is of the utmost importance for safe operation. A combined atom probe field-ion microscopy (APFIM) and transmission electron microscopy (TEM) study was performed to characterize the microstructure of this cast stainless steel and to determine the changes that occur during long-term low-temperature thermal aging. The material used in this investigation was a commercial CF 8 type stainless. The steel was examined in the as-cast, unaged condition and also after aging for 7500 h at 673K. 3 refs., 4 figs., 2 tabs
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Ter...
In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials remov...
To investigate the effect of long-term thermal aging on the fusion boundary region between low-alloy...
Atom probe field-ion microscopy, analytical electron microscopy, and optical microscopy have been us...
La microscopie ionique de champ et l'analyse par sonde atomique et la microscopie électronique par t...
Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricate...
The effects of thermal aging time at 400 °C on the microstructure and mechanical and corrosion behav...
Microstructural investigations of thermally aged nuclear grade type 316L stainless steel welds were ...
Stainless steels have been used for decades in nuclear power stations, particularly in pipe and tube...
The present investigation indicates that the primary embrittlement processes of the CF-8 grade cast ...
The combined effect of thermal aging and irradiation on cast and welded stainless steel solidificati...
This thesis studiesthe microstructural evolution of welded austenitic stainless steels that are comm...
Z3CN20.09M cast duplex stainless steel (CDSS) has been used for primary coolant water pipes in press...
To study the thermal aging of nuclear primary pipe material 316LN stainless steel weld, accelerated ...
Atom probe field ton microscopy (APFIM) investigations of the microstructure of as-fabricated, long-...
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Ter...
In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials remov...
To investigate the effect of long-term thermal aging on the fusion boundary region between low-alloy...
Atom probe field-ion microscopy, analytical electron microscopy, and optical microscopy have been us...
La microscopie ionique de champ et l'analyse par sonde atomique et la microscopie électronique par t...
Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricate...
The effects of thermal aging time at 400 °C on the microstructure and mechanical and corrosion behav...
Microstructural investigations of thermally aged nuclear grade type 316L stainless steel welds were ...
Stainless steels have been used for decades in nuclear power stations, particularly in pipe and tube...
The present investigation indicates that the primary embrittlement processes of the CF-8 grade cast ...
The combined effect of thermal aging and irradiation on cast and welded stainless steel solidificati...
This thesis studiesthe microstructural evolution of welded austenitic stainless steels that are comm...
Z3CN20.09M cast duplex stainless steel (CDSS) has been used for primary coolant water pipes in press...
To study the thermal aging of nuclear primary pipe material 316LN stainless steel weld, accelerated ...
Atom probe field ton microscopy (APFIM) investigations of the microstructure of as-fabricated, long-...
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Ter...
In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials remov...
To investigate the effect of long-term thermal aging on the fusion boundary region between low-alloy...