Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel

2005 ◽  
Vol 2 (3) ◽  
pp. 12399 ◽  
Author(s):  
R Kasada ◽  
T Kudo ◽  
A Kimura ◽  
H Matsui ◽  
M Narui
Keyword(s):  
Dose Rate ◽  
Pressure Vessel ◽  
Irradiation Temperature ◽  
Reactor Pressure Vessel ◽  
Neutron Dose ◽  
Pressure Vessel Steel ◽  
Irradiation Embrittlement ◽  
Vessel Steel ◽  
Reactor Pressure Vessel Steel ◽  
Reactor Pressure

Influence of the Irradiation Temperature on the Formation of Defects in Reactor Pressure Vessel Steels

1996 ◽  
Vol 439 ◽  
Author(s):  
M. Große ◽  
A. Hempel ◽  
J. Böhmert ◽  
G. Brauer ◽  
F. M. Haggag
Keyword(s):  
Pressure Vessel ◽  
Irradiation Temperature ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel ◽  
Post Irradiation ◽  
Cu Content ◽  
Reactor Pressure Vessel Steel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

AbstractTwo heats of reactor pressure vessel steel type A533-B-1 differing in their Cu content (0.07 and 0.14 wt.-%) were irradiated to a fluence of 1* 1018 neutrons/cm2 at temperatures of 60, 121, and 288 °C, respectively. Their microstructure has been studied by SANS, SAXS, and PAS in the asirradiated and post-irradiation annealed stages and compared to the behaviour of unirradiated material and the results are discussed.

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