Remediation of 137Cs radionuclide in nuclear waste effluents by polymer composite: adsorption kinetics, isotherms and gamma irradiation studies

2018 ◽  
Vol 316 (3) ◽  
pp. 933-945 ◽  
Author(s):  
Michael A. Olatunji ◽  
Mayeen U. Khandaker ◽  
Ekramul H. N. M. Mahmud ◽  
Yusoff Md. Amin ◽  
Janet A. Ademola ◽  
...  
1989 ◽  
Vol 176 ◽  
Author(s):  
P. Van Iseghem ◽  
K. Berghman ◽  
W. Timmermans

ABSTRACTThe interaction between simulated HLW glasses and clay has been investigated, as part of a larger programme to evaluate the performance of vitrified HLW in repository conditions. Experimental conditions were carefully chosen to simulate repository conditions as close as possible. The glass corrosion seems to be controlled by a diffusion process, but there are indications of a (small) final corrosion rate. The leaching of 134Cs, 90Sr, 239Pu and 241Am is characterized by extremely small mobile concentrations leached (for 239pu and 241Am, below detection limit). The presence of a gamma irradiation field does not increase the glass dissolution. The production of radiolythic hydrogen is strongly reduced by the presence of clay.


1985 ◽  
Vol 91 (1-2) ◽  
pp. 89-96 ◽  
Author(s):  
J. F. Denatale ◽  
D. G. Howitt

2015 ◽  
Vol 30 (9) ◽  
pp. 1563-1571 ◽  
Author(s):  
Neda Mobasher ◽  
Susan A. Bernal ◽  
Hajime Kinoshita ◽  
Clint A. Sharrad ◽  
John L. Provis

Abstract


2019 ◽  
Vol 86 (10) ◽  
pp. 608
Author(s):  
N. M. Romanov ◽  
F. M. Shakhov ◽  
V. Yu. Osipov ◽  
C. F. Musikhin

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