In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing

Materialia ◽  
2020 ◽  
Vol 12 ◽  
pp. 100778
Author(s):  
Yufeng Du ◽  
Kenta Yoshida ◽  
Yusuke Shimada ◽  
Takeshi Toyama ◽  
Koji Inoue ◽  
...  
Keyword(s):  
Dislocation Loop ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel ◽  
Post Irradiation ◽  
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.

Evolution of precipitation in reactor pressure vessel steel welds under neutron irradiation

2017 ◽  
Vol 488 ◽  
pp. 222-230 ◽  
Author(s):  
Kristina Lindgren ◽  
Magnus Boåsen ◽  
Krystyna Stiller ◽  
Pål Efsing ◽  
Mattias Thuvander
Keyword(s):  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel ◽  
Reactor Pressure Vessel Steel ◽  
Steel Welds ◽  
Reactor Pressure
Sign in / Sign up

Export Citation Format

Share Document