Stress corrosion cracking and corrosion fatigue of nuclear reactor pressure vessel steels in hot water

1987 ◽  
Vol 9 (2) ◽  
pp. 157-162 ◽  
Author(s):  
M. O. Speidel
Keyword(s):  
Stress Corrosion ◽  
Corrosion Fatigue ◽  
Stress Corrosion Cracking ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Corrosion Cracking ◽  
Reactor Pressure Vessel ◽  
Hot Water ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

Stress Corrosion Cracking Susceptibility of Low Alloy Steels Used for Reactor Pressure Vessel in High Temperature Oxygenated Water

1985 ◽  
Vol 107 (4) ◽  
pp. 430-435 ◽  
Author(s):  
J. Kuniya ◽  
I. Masaoka ◽  
R. Sasaki ◽  
H. Itoh ◽  
T. Okazaki
Keyword(s):  
Dissolved Oxygen ◽  
Strain Rate ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Pressure Vessel ◽  
Corrosion Cracking ◽  
Reactor Pressure Vessel ◽  
Low Alloy Steels ◽  
Alloy Steels ◽  
Reactor Pressure

Studies have been done on stress corrosion cracking (SCC) susceptibility of low alloy steels in water containing dissolved oxygen. The fundamental factors which affect the SCC susceptibility were clarified, and the integrity of the reactor pressure vessel (RPV), in which these steels are used, was assessed from the standpoint of SCC initiation. The effects of applied stress, strain rate, dissolved oxygen concentration, and test temperatures, on the SCC susceptibility was examined utilizing uniaxial constant load tensile tests (UCL), and slow strain rate tests (SSRT).

701 Surveillance Test Specimens of Nuclear Reactor Pressure Vessel Steels analyzed by 3D Atom Probe and Positron Annihilation

2006 ◽  
Vol 2006 (0) ◽  
pp. 379-380
Author(s):  
Yasuyoshi NAGAI ◽  
Takeshi TOYAMA ◽  
Zheng TANG ◽  
Masayuki HASEGAWA ◽  
Abderrahim Almazouzi ◽  
...  
Keyword(s):  
Positron Annihilation ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Atom Probe ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure
Sign in / Sign up

Export Citation Format

Share Document