Fluence reduction of nuclear reactor pressure vessels by fuel-management strategies

1986 ◽  
Vol 13 (2) ◽  
pp. 85-91 ◽  
Author(s):  
H. Fenech ◽  
K. Tsai
Keyword(s):  
Nuclear Reactor ◽  
Management Strategies ◽  
Pressure Vessels ◽  
Fuel Management ◽  
Reactor Pressure

Comparative analysis and verification of engineering methods of shallow cracks effect for fracture toughness prediction for reactor pressure vessels

2020 ◽  
pp. 140-165
Author(s):  
V. I. Kostylev ◽  
B. Z. Margolin
Keyword(s):  
Experimental Data ◽  
Fracture Toughness ◽  
Comparative Analysis ◽  
Nuclear Reactor ◽  
Probabilistic Approach ◽  
Pressure Vessels ◽  
Local Methods ◽  
European Method ◽  
Shallow Crack ◽  
Reactor Pressure

The main features of shallow cracks fracture are considered, and a brief analysis of methods allowing to predict the temperature dependence of the fracture toughness KJC (T) for specimens with shallow cracks is given. These methods include DA-method, (JQ)-method, (J-T)-method, “local methods” with its multiparameter probabilistic approach, GP method uses power approach, and also two engineering methods – RMSC (Russian Method for Shallow Crack) and EMSC (European Method for Shallow Crack). On the basis of 13 sets of experimental data for national and foreign steels, a detailed verification and comparative analysis of these two engineering methods were carried out on the materials of the VVER and PWR nuclear reactor vessels considering the effect of shallow cracks.

Embrittlement of nuclear reactor pressure vessels

JOM ◽  
2001 ◽  
Vol 53 (7) ◽  
pp. 18-22 ◽  
Author(s):  
G. R. Odette ◽  
G. E. Lucas
Keyword(s):  
Nuclear Reactor ◽  
Pressure Vessels ◽  
Reactor Pressure
Sign in / Sign up

Export Citation Format

Share Document