A comparison of Western and Eastern nuclear reactor pressure vessel steels

1999 ◽  
Vol 76 (3) ◽  
pp. 163-208 ◽  
Author(s):  
L.M Davies
2006 ◽  
Vol 2006 (0) ◽  
pp. 379-380
Author(s):  
Yasuyoshi NAGAI ◽  
Takeshi TOYAMA ◽  
Zheng TANG ◽  
Masayuki HASEGAWA ◽  
Abderrahim Almazouzi ◽  
...  

1982 ◽  
Vol 68 (8) ◽  
pp. 1032-1039 ◽  
Author(s):  
Tsuneo KODAIRA ◽  
Nobuya NAKAJIMA ◽  
Masakatsu MATSUMOTO ◽  
Kiyoshi FUKAYA

2013 ◽  
Vol 592-593 ◽  
pp. 577-581 ◽  
Author(s):  
Oleg O. Zabusov ◽  
Boris A. Gurovich ◽  
Evgenia A. Kuleshova ◽  
Michail A. Saltykov ◽  
Svetlana V. Fedotova ◽  
...  

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.


Author(s):  
Karim Serasli ◽  
Harry Coules ◽  
David Smith

Most residual stress measurement methods are limited in terms of their stress and spatial resolution, number of stress tensor components measured and measurement uncertainty. In contrast, finite element simulations of welding processes provide full field distributions of residual stresses, with results dependent on the quality of the input conditions. Measurements and predictions are often not the same, and the true residual stress state is difficult to determine. In this paper both measurements and predictions of residual stresses, created in clad nuclear reactor pressure vessel steels, are made. The measurements are then used as input to a residual stress mapping technique provided within a finite element analysis. The technique is applied iteratively to converge to a balanced solution which is not necessarily unique. However, the technique aids the identification of locations for additional measurements. This is illustrated in the paper. The outcomes from the additional measurements permit more realistic and reliable estimates of the true residual state to be made. The outcomes are compared with the finite element simulations of the welding process and used to determine whether there is a need for additional input to the simulations.


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