Revisiting the Use of SiC as a Post Irradiation Temperature Monitor

Author(s):  
LL Snead ◽  
AM Williams ◽  
AL Qualls
1996 ◽  
Vol 439 ◽  
Author(s):  
M. Große ◽  
A. Hempel ◽  
J. Böhmert ◽  
G. Brauer ◽  
F. M. Haggag

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.


2019 ◽  
Vol 963 ◽  
pp. 362-366
Author(s):  
Jonas Vande Pitte ◽  
Christophe Detavernier ◽  
Johan Lauwaert ◽  
Inge Uytdenhouwen ◽  
Andrei Gusarov ◽  
...  

Post-irradiation data on the neutron-induced swelling behaviour and resistivity changes in silicon carbide often does not show a clear trend. This makes a quantitative comparison between different studies difficult. To address the diverging results after irradiation in different studies, a thorough reference study is performed on high quality β-silicon carbide. The results show the response to neutron irradiation may be significantly influenced by structural defects present before irradiation. These findings open a way to improve the accuracy of silicon carbide irradiation temperature monitors.


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