scholarly journals MEASURED LOSS OF SELECTED FISSION PRODUCTS FROM HIGH-BURNUP MIXED-OXIDE FUEL IN A MINIATURE PUMPED SODIUM LOOP.

1971 ◽  
Author(s):  
D.E. Plumlee ◽  
P.E. Novak
1972 ◽  
Vol 16 (1) ◽  
pp. 110-119 ◽  
Author(s):  
M. Coquerelle ◽  
J. Gabolde ◽  
R. Lesser ◽  
P. Werner

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

2008 ◽  
Vol 161 (1) ◽  
pp. 35-44 ◽  
Author(s):  
Philippe Martin ◽  
Michel Pelletier ◽  
Denis Every ◽  
Derek Buckthorpe

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


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