Feasibility studies for the detection of third phase during reprocessing of fast reactor fuel

2011 ◽  
Vol 292 (2) ◽  
pp. 879-883 ◽  
Author(s):  
S. Subbuthai ◽  
R. Ananthanarayanan ◽  
P. Sahoo ◽  
A. Nageswara Rao ◽  
R. V. Subba Rao
Keyword(s):  
Fast Reactor ◽  
Feasibility Studies ◽  
Reactor Fuel ◽  
Third Phase ◽  
Fast Reactor Fuel

Feasibility studies of using N,N-dihexyloctanamide (DHOA) for fast reactor fuel reprocessing applications

energyo ◽  
2019 ◽  
Author(s):  
Jammu Ravi ◽  
Satyabrata Mishra ◽  
N. K. Pandey ◽  
C. Mallika ◽  
U. Kamachi Mudali
Keyword(s):  
Fast Reactor ◽  
Feasibility Studies ◽  
Reactor Fuel ◽  
Fast Reactor Fuel ◽  
Fuel Reprocessing

Feasibility studies of using N,N-dihexyloctanamide (DHOA) for fast reactor fuel reprocessing applications

2018 ◽  
Vol 106 (4) ◽  
pp. 311-317 ◽  
Author(s):  
Jammu Ravi ◽  
Satyabrata Mishra ◽  
N. K. Pandey ◽  
C. Mallika ◽  
U. Kamachi Mudali
Keyword(s):  
Physical Properties ◽  
Fast Reactor ◽  
Feasibility Studies ◽  
Reactor Fuel ◽  
Extraction Behavior ◽  
Ir Studies ◽  
Ft Ir ◽  
Fast Reactor Fuel ◽  
Duration Of Heating ◽  
Fuel Reprocessing

AbstractN,N-dihexyloctanamide (DHOA) is being considered as a promising extractant in the aqueous reprocessing of spent nuclear fuels. In view of rise in temperature of the solvent during reprocessing of fast reactor fuel, the present study aimed at evaluating the physical properties such as density, viscosity, and interfacial tension and Pu(IV) extraction behavior in 1.1 M DHOA/n-dodecane as a function of temperature and duration of heating. The influence of nitric acid in altering the physical properties with respect to temperature was evaluated. Physical properties and extraction behavior of the solvent changed to a remarkable extent with temperature. Quantitative amount of Pu(IV) could be back-extracted from loaded, solvent in three contacts at 313 K. FT-IR studies were carried out to evaluate the thermal stability of the solvent. Thus, the performance of the solvent, 1.1 M DHOA/n-dodecane is satisfactory at higher temperatures also.

Current Status of the Development of the Fast Reactor Fuel Cycle in India

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Current Status ◽  
Fast Reactor Fuel

COMPUTATIONAL FLUID DYNAMIC INVESTIGATIONS ON EFFECTS OF CIRCULAR ROD INSERTS IN FAST REACTOR FUEL BUNDLE

2018 ◽  
Author(s):  
G Padmakumar ◽  
K. Velusamy ◽  
Bhamidi V. S. S. S. Prasad ◽  
P Lijukrishnan ◽  
P. Selvaraj
Keyword(s):  
Fast Reactor ◽  
Computational Fluid Dynamic ◽  
Fluid Dynamic ◽  
Reactor Fuel ◽  
Fuel Bundle ◽  
Fast Reactor Fuel

Fast Reactor Fuel Burnup

1965 ◽  
Vol 1 (1) ◽  
pp. 55-61 ◽  
Author(s):  
F. R. Channon ◽  
J. D. Luoma ◽  
E. D. Frankhouser
Keyword(s):  
Fast Reactor ◽  
Reactor Fuel ◽  
Fuel Burnup ◽  
Fast Reactor Fuel

scholarly journals The Effect Assessment for Fast Reactor Fuel Cycle Deployment-improvement of the Assessment Method-

2013 ◽  
Vol 39 ◽  
pp. 43-51
Author(s):  
Kyoko Mukaida ◽  
Hiroki Shiotani ◽  
Kiyoshi Ono ◽  
Takashi Namba
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Assessment Method ◽  
Reactor Fuel ◽  
Effect Assessment ◽  
Fast Reactor Fuel
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