Ionic Liquids for the Nuclear Industry: A Radiochemical, Structural, and Electrochemical Investigation

2002 ◽  
pp. 162-177 ◽  
Author(s):  
G. M. N. Baston ◽  
A. E. Bradley ◽  
T. Gorman ◽  
I. Hamblett ◽  
C. Hardacre ◽  
...  
Keyword(s):  
Ionic Liquids ◽  
Nuclear Industry ◽  
Electrochemical Investigation

Electrochemical Investigation of Quaternary Ammonium/Aluminum Chloride Ionic Liquids

2004 ◽  
Vol 151 (8) ◽  
pp. A1168 ◽  
Author(s):  
K. Kim ◽  
Christopher Lang ◽  
Roger Moulton ◽  
Paul A. Kohl
Keyword(s):  
Ionic Liquids ◽  
Aluminum Chloride ◽  
Quaternary Ammonium ◽  
Electrochemical Investigation

Ionic Liquids in the Nuclear Industry

2003 ◽  
pp. 209-226 ◽  
Author(s):  
W. R. Pitner ◽  
A. E. Bradley ◽  
D. W. Rooney ◽  
D. Sanders ◽  
K. R. Seddon ◽  
...  
Keyword(s):  
Ionic Liquids ◽  
Nuclear Industry

Biredox ionic liquids: electrochemical investigation and impact of ion size on electron transfer

2016 ◽  
Vol 206 ◽  
pp. 513-523 ◽  
Author(s):  
Eléonore Mourad ◽  
Laura Coustan ◽  
Stefan A. Freunberger ◽  
Ahmad Mehdi ◽  
André Vioux ◽  
...  
Keyword(s):  
Electron Transfer ◽  
Ionic Liquids ◽  
Electrochemical Investigation ◽  
Ion Size

Point Defect Absorption and Dislocation Loop Formation at Grain Boundaries in Hvem-Irradiated Zr and Its Alloys:1. Influence of Solute Addition

1985 ◽  
Vol 43 ◽  
pp. 350-351
Author(s):  
R.A. Herring ◽  
M. Griffiths ◽  
M.H Loretto ◽  
R.E. Smallman
Keyword(s):  
Grain Boundary ◽  
Grain Boundaries ◽  
Point Defect ◽  
Reactor Core ◽  
Solute Concentration ◽  
Nuclear Industry ◽  
Dislocation Loops ◽  
Loop Formation ◽  
Component Material ◽  
Impurity Interaction

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.

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