Treatment of Simulated High-Level Radioactive Waste with Formic Acid: Bench-Scale Study on Hydrogen Evolution

1996 ◽  
Vol 116 (2) ◽  
pp. 196-207 ◽  
Author(s):  
Chia-Lin W. Hsu ◽  
James A. Ritter
1993 ◽  
Vol 104 (3) ◽  
pp. 330-342 ◽  
Author(s):  
James A. Ritter ◽  
John R. Zamecnik ◽  
Chia-Lin W. Hsu

1981 ◽  
Vol 6 ◽  
Author(s):  
Russell E. Eibling ◽  
John R. fowler

ABSTRACTA reference process for immobilizing the high-level radioactive waste in borosilicate glass has been developed at the Savannah River Plant. This waste contains a substantial amount of mercury from separations processing. Because mercury will not remain in borosilicate glass at the processing temperature, mercury must be removed before vitrification or must be handled in the off-gas system. A process has been developed to remove mercury by reduction with formic acid prior to vitrification. Additional benefits of formic acid treatment include improved sludge handling and glass melter redox control.


1994 ◽  
Vol 187 (1) ◽  
pp. 19-24 ◽  
Author(s):  
V. Guyon ◽  
A. Guy ◽  
J. Foos ◽  
R. Chomel ◽  
T. Moutarde ◽  
...  

2003 ◽  
pp. 203-208
Author(s):  
Hideo KOMINE ◽  
Nobuhide OGATA ◽  
Akira NAKASHIMA ◽  
Hajime TAKAO ◽  
Hiroyoshi UEDA ◽  
...  

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