scholarly journals Separation of Uranyl Nitrate HexahydrateCrystal from Dissolver Solution of IrradiatedFast Neutron Reactor Fuel

10.5772/34913 ◽  
2012 ◽  
Author(s):  
Masaumi Nakahara
Keyword(s):  
Uranyl Nitrate ◽  
Reactor Fuel ◽  
Dissolver Solution ◽  
Neutron Reactor

Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal

2010 ◽  
Vol 98 (6) ◽  
Author(s):  
M. Nakahara ◽  
K. Nomura ◽  
T. Washiya ◽  
T. Chikazawa ◽  
I. Hirasawa
Keyword(s):  
Uranyl Nitrate ◽  
Mixed Oxide ◽  
Crystallization Process ◽  
Fission Products ◽  
Nitrate Hexahydrate ◽  
Oxide Fuel ◽  
Uranyl Nitrate Hexahydrate ◽  
Mixed Oxide Fuel ◽  
Mox Fuel ◽  
Dissolver Solution

AbstractIn order to examine the decontamination behavior of the Pu and fission products (FPs) that contained with the uranyl nitrate hexahydrate (UNH) crystals in the U crystallization process, experiments were carried out using mixed oxide (MOX) fuel dissolver solution. The experiments confirmed that Eu was adequately decontaminated by washing the UNH crystals with a HNO

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
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