scholarly journals A Study on Embrittlement of Fast Neutron-irradiated Nuclear Reactor Pressure Vessel Steels at Room- and Liquid Nitrogen-temperature

2005 ◽  
Vol 15 (2) ◽  
pp. 142-147
Author(s):  
H.B. Kim ◽  
H.S. Kim ◽  
S.K. Kim ◽  
D.H. Shin ◽  
Y.B. Yu ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Liquid Nitrogen ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Liquid Nitrogen Temperature ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

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

scholarly journals JIC Fracture Toughness of Nuclear Reactor Pressure Vessel Steels in Transition and Upper Shelf Regions

1982 ◽  
Vol 68 (8) ◽  
pp. 1032-1039 ◽  
Author(s):  
Tsuneo KODAIRA ◽  
Nobuya NAKAJIMA ◽  
Masakatsu MATSUMOTO ◽  
Kiyoshi FUKAYA
Keyword(s):  
Fracture Toughness ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels

2013 ◽  
Vol 592-593 ◽  
pp. 577-581 ◽  
Author(s):  
Oleg O. Zabusov ◽  
Boris A. Gurovich ◽  
Evgenia A. Kuleshova ◽  
Michail A. Saltykov ◽  
Svetlana V. Fedotova ◽  
...  
Keyword(s):  
Brittle Fracture ◽  
Grain Boundaries ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Reactor Pressure Vessel ◽  
Operating Conditions ◽  
Fracture Surfaces ◽  
Intergranular Embrittlement ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

Service life of VVER-type nuclear reactor is limited by decrease in brittle fracture resistance of reactor pressure vessel produced of low-alloy low-carbon steel under effect of irradiation and/or elevated temperatures. In this work fracture surfaces were studied by Auger-electron spectroscopy in order to estimate the contribution of intergranular embrittlement to the degradation of reactor pressure vessel steels under the influence of operating conditions. It was demonstrated that irradiation induced segregation leads to an increase of P content in grain boundaries that promotes intergranular brittle fracture on fracture surfaces. The similar effect but to a lesser degree was shown in the case of long-term temperature exposure. The grain boundary structure was examined and an effect of carbides located on the grain boundaries is supposed due to increased phosphorus segregation on carbide/matrix interface boundaries.

Sign in / Sign up

Export Citation Format

Share Document