Microstructural Development of Titanium-Modified Austenitic Stainless Steel Under Neutron Irradiation in HFIR up to 57 dpa

Author(s):  
M Suzuki ◽  
S Hamada ◽  
PJ Maziasz ◽  
MP Tanaka ◽  
A Hishinuma
2021 ◽  
Vol 1024 ◽  
pp. 53-69
Author(s):  
Eiichi Wakai ◽  
Shuhei Nogami ◽  
Akira Hasegawa ◽  
Nariaki Okubo ◽  
Shigeru Takaya ◽  
...  

The effects of helium concentration and displacement damage on microstructural evolution at low dpa and low helium concentration were mainly investigated in specimens of austenitic stainless steel 316FR or SUS304 and a high chromium martensitic steel (HCM12A). The 316FR and HCM12A specimens were implanted uniformly with helium at 823 K up to 30 appm-He or 50 appm-He by 50 MeV cyclotron accelerator using energy degraders. After the helium implantation, the microstructures were examined by a transmission electron microscopy and positron annihilation lifetime measurements. Irradiation hardening behaviors were analyzed using SUS304 and HCM12A steels at 823 K implanted with He ion up to 100 appm with different He/dpa ratios in the HIT ion irradiation experiments and the hardening behaviors were examined by nano indentation method. In the irradiation and annealing specimens, these mechanical properties and microstructures were examined to understand the effects of helium production, displacement damage and annealing on microstructural development, and kinetic Monte Carlo (kMC) simulations were also performed to understand the microstructural development, and the results were compared with the results of TEM observation and positron annihilation lifetime measurements. Important some differences in the microstructural developments such as cavity formation and growth between austenitic stainless steel and martensitic steel were observed in low dpa and low helium concentration conditions.


2021 ◽  
Vol 544 ◽  
pp. 152680
Author(s):  
Valentin K. Shamardin ◽  
Tatyana M. Bulanova ◽  
Alexander E. Fedoseev ◽  
Alexei A. Karsakov ◽  
Ruslan Z. Valiev ◽  
...  

Author(s):  
P. J. Maziasz ◽  
R. W. Carpenter

MC precipitate particles in austenitic stainless steels have an important and unique effect on radiation response of these materials in a fusion reactor environment.Radiation-generated helium agglomerates at the precipitate/matrix interfaces in the form of small bubbles. There are two morphological variants of the precipitate and both have similar helium trapping behavior. In this note we describe initial observations of one crystallographic and morphological variant of MC in austenite, which is the dominant variant formed during neutron irradiation in HFIR.


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