Size-Distribution of Irradiation-Induced Dislocation-Loops in Materials Used in the Nuclear Industry

2021 ◽  
pp. 152945
Author(s):  
Tamás Ungár ◽  
Philipp Frankel ◽  
Gábor Ribárik ◽  
Christopher P. Race ◽  
Michael Preuss
Author(s):  
R.A. Herring ◽  
M. Griffiths ◽  
M.H Loretto ◽  
R.E. Smallman

Because Zr is used in the nuclear industry to sheath fuel and as structural component material within the reactor core, it is important to understand Zr's point defect properties. In the present work point defect-impurity interaction has been assessed by measuring the influence of grain boundaries on the width of the zone denuded of dislocation loops in a series of irradiated Zr alloys. Electropolished Zr and its alloys have been irradiated using an AEI EM7 HVEM at 1 MeV, ∼675 K and ∼10-6 torr vacuum pressure. During some HVEM irradiations it has been seen that there is a difference in the loop nucleation and growth behaviour adjacent to the grain boundary as compared with the mid-grain region. The width of the region influenced by the presence of the grain boundary should be a function of the irradiation temperature, dose rate, solute concentration and crystallographic orientation.


2021 ◽  
Vol 27 ◽  
pp. 101007
Author(s):  
K. Vogel ◽  
P. Chekhonin ◽  
C. Kaden ◽  
M. Hernández-Mayoral ◽  
S. Akhmadaliev ◽  
...  

2019 ◽  
Vol 102 (12) ◽  
pp. 7533-7542 ◽  
Author(s):  
Marat Khafizov ◽  
Janne Pakarinen ◽  
Lingfeng He ◽  
David H. Hurley

2005 ◽  
Vol 97 (7) ◽  
pp. 073512 ◽  
Author(s):  
M. Milosavljević ◽  
G. Shao ◽  
M. A. Lourenco ◽  
R. M. Gwilliam ◽  
K. P. Homewood

2016 ◽  
Vol 725 ◽  
pp. 189-194
Author(s):  
Ying Ying Cai ◽  
Jia Pei Guo ◽  
Yi Ping Chen

At the microscopic scale fast neutron irradiation brings about a high density of small point defect clusters in the form of dislocation loops and voids. And such radiation damage is of primary importance for materials used in nuclear energy production. In the present investigation emphasis is placed on the understanding of the mechanisms involved in the evolution of prismatic dislocation loops by glide in the presence of external free surfaces and those of the voids and in the interaction between dislocation loops and voids within irradiated thin films, so as to simulate in situ Transmission Electron Microscopy (TEM) images of dislocations, which is an indispensable tool for extracting information on radiation damage. By employing 3D dislocation dynamics based on isotropic elacticity and principle of superposition, the calculation results show that the image force is determined by the distance of the dislocation loop from the external and void surfaces and scales with the film thickness; the dislocation glide force is determined by the image stress as well as the loop–loop interaction stress which is in turn governed by the loop spacing. It is also shown that the presence of voids in the thin films has a strong influence on the behaviours of prismatic dislocations.


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