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

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

1999 ◽  
Vol 273 (3) ◽  
pp. 239-247 ◽  
Author(s):  
I. Sato ◽  
H. Furuya ◽  
T. Arima ◽  
K. Idemitsu ◽  
K. Yamamoto

2005 ◽  
Author(s):  
S. A. Hodge ◽  
R. N. Morris ◽  
L. J. Ott

2021 ◽  
pp. 1-9
Author(s):  
Richard M. Ambrosi ◽  
Daniel P. Kramer ◽  
Emily Jane Watkinson ◽  
Ramy Mesalam ◽  
Alessandra Barco

2000 ◽  
Vol 307 (1-2) ◽  
pp. 1-9 ◽  
Author(s):  
Kazuhiro Yamada ◽  
Ken Kurosaki ◽  
Msayoshi Uno ◽  
Shinsuke Yamanaka

1992 ◽  
Vol 188 ◽  
pp. 154-161 ◽  
Author(s):  
T. Abe ◽  
N. Nakae ◽  
K. Kodato ◽  
M. Matsumoto ◽  
T. Inabe

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