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

Experimental and Computational Investigations of Heat Transfer and Stability of Boiling Liquid Metal in a Model of an Array of the Fast-Neutron Reactor Fuel Elements

2001 ◽  
Vol 32 (1-3) ◽  
pp. 9
Author(s):  
A. D. Efanov ◽  
E. F. Ivanov ◽  
V. P. Kolesnik ◽  
O. A. Korkhov ◽  
V. L. Mal'kov ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Liquid Metal ◽  
Fast Neutron ◽  
Reactor Fuel ◽  
Fast Neutron Reactor ◽  
Boiling Liquid ◽  
Neutron Reactor ◽  
Fuel Elements

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

Partitioning of Plutonium by Acid Split Method with Dissolver Solution Derived from Irradiated Fast Reactor Fuel with High Concentration of Plutonium

2018 ◽  
Vol 51 (3) ◽  
pp. 237-242 ◽  
Author(s):  
Masaumi Nakahara ◽  
Yuichi Sano ◽  
Kazunori Nomura ◽  
Masayuki Takeuchi
Keyword(s):  
Fast Reactor ◽  
Reactor Fuel ◽  
High Concentration ◽  
Split Method ◽  
Dissolver Solution ◽  
Fast Reactor Fuel

scholarly journals Influence of Boric Acid in the Extraction of Uranium (VI), Plutonium (IV) and Europium (III) from Fast Reactor Fuel Dissolver Solution

2008 ◽  
Vol 9 (2) ◽  
pp. 37-39 ◽  
Author(s):  
K.A. Venkatesan ◽  
V. Sukumaran ◽  
M.P. Antony ◽  
T.G. Srinivasan
Keyword(s):  
Boric Acid ◽  
Fast Reactor ◽  
Reactor Fuel ◽  
Dissolver Solution ◽  
Fast Reactor Fuel

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

Hydrothermal precipitation of uranium dioxide from uranyl nitrate solutions

1966 ◽  
Vol 16 (6) ◽  
pp. 187-190
Author(s):  
R. G. Robins
Keyword(s):  
Uranium Dioxide ◽  
Uranyl Nitrate ◽  
Hydrothermal Precipitation ◽  
Nitrate Solutions
Sign in / Sign up

Export Citation Format

Share Document