Cs batch sorption and column transport experiments on sand from the Yamin plain, Israel – Experimental results and modelling

Author(s):  
Ofra Klein-BenDavid ◽  
Noa Balaban ◽  
Svetlana Gelfer ◽  
Ronen Komerian ◽  
David Saban ◽  
...  

<p>The Yanim plain hosts the national Israeli radioactive waste disposal site. The site is located on the Miocene aged Hazeva formation, comprised of loose sand, sandstone and dispersed clay layers. The current research examines the sorption capacity of the local sand to solutions doped with Cs ions. The sand contains ~95% quartz and ~5% of various clays, carbonates, and oxides. Batch sorption experiments were conducted at a liquid to solid ratio of 10. Two end-member solutions were used, fresh (MQ) and concentrated (Na-Nitrate solution). Both solutions were doped with 0.1, 1, 10, 100 and 1000 ppm of Cs (as a nitrate). For the MQ experiments Kd values ranged between ~2 and ~1300, where the highest Kds were registered for the 1 ppm doping level, and the smallest Kds were for the 1000 ppm doping level. For the concentrated solution Kd values ranged between ~0 and ~1.5, where the highest Kds were for the 1 ppm doping level, for all other doping levels Kds were <1. Freundlich and Langmuir isotherm calculations revealed a significantly better correlation on a linearized Freundlich isotherm, indicating a multi-layer and multi-site sorption model, with a similar slope for both solutions, indicating a common sorption mechanism. Column transport experiments (L=25cm, r=2cm, φ=30%, 1PV=180cc) have shown minimal retardation of the Cs in the concentrated solution flow experiments (R= ~2). A second, probably colloid-related peak, showed an early breakthrough with respect to a conservative color tracer.  On the other hand, when MQ was run in the column no breakthrough was observed within 10 column pore volumes. In one fresh experiment a very small colloid related peak was found with breakthrough similar to the conservative tracer. We used the CXTFIT model to calculated the dispersity (λ [L]) and normalized velocity (V) of the measured tracer. For the conservative tracer the values were λ=0.13 cm and V=0.9 cm. For Cs transport in the concentrated solution λ=0.22 cm and V=1.6. Thus, it may be concluded that even in similar doping levels in the same matrix the solution chemistry will play a major role in contaminant retardation. Thus, rain episodes which abruptly change the solution chemistry, can significantly affect solute and colloid mobility.</p>

2010 ◽  
Vol 27 (3) ◽  
pp. 231-239 ◽  
Author(s):  
Michael J. Wilkins ◽  
Francis R. Livens ◽  
David J. Vaughan ◽  
Jonathan R. Lloyd ◽  
Ian Beadle ◽  
...  

2019 ◽  
Vol 197 ◽  
pp. 174-183 ◽  
Author(s):  
Abdel-Aal M. Abdel-Karim ◽  
Ahmed A. Zaki ◽  
Waheed Elwan ◽  
Mohamed R. El-Naggar ◽  
Mahmoud M. Gouda

2005 ◽  
Author(s):  
L. Vértesy ◽  
Á. Gulyás ◽  
A. Madarasi ◽  
P. Kovács ◽  
L. Sörés ◽  
...  

Author(s):  
A. Dreimanis

Management of decommissioning waste is considered as complex task of seeking for optimal solution in the environment of various competing technical, safety and socio-economical factors. If from the formal mathematics viewpoint it is a multi-parameter optimization task, then for real conditions simplified approach for such problem should be applied. We propose to decompose this task into the set of optimization analysis for particular steps, and then in each step it is easier to find optimum. For the real case of management of radioactive waste arising from dismantling and decommissioning of Salaspils Research Reactor (SRR) we consider following main optimization steps: 1) the choice of the decommissioning concept — among three elaborated versions — with estimation of the foreseen radioactive waste amount for disposal, recycling and free release, taking into account also potential exposures and financial resources; 2) establishment of national radioactive waste management agency “RAPA” Ltd., ensuring common administration and maintenance of the shutdown SRR and radioactive waste (RW) disposal site — RAPA manages some decommissioning activities of SRR and shall actively participate together with envisaged decommissioning operator in this process also in future, but in all stages will keep full responsibility of waste management; 3) optimization of radioactive waste transportation: i) organizational aspects (packing, transportation time, schedule, route, etc.), ii) environmental safety control; 4) optimization arrangement of space for radioactive waste disposal: i) choice of the best strategy to ensure a new space, ii) optimization of the vault size — to be able accommodate decommissioning waste without being oversized; 5) strategy of treatment, conditioning and packing of solid decommissioning waste; 6) optimization of liquid decommissioning waste management — its conditioning together with the solid radioactive waste; 7) socio-economical optimization features: i) existing infrastructure for RW disposal, ii) financial compensation for local municipality, iii) international cooperation, technical and financial assistance by EU, IAEA, Sweden. The proposed optimization features used in the developing of Concept for radioactive waste management in Latvia for the period 2003–2010 (which corresponds to the approved decommissioning period of SRR) supplement existing separate optimization aspects of decommissioning waste management and could be considered as simplified integral set of factors for elaboration of optimal strategy for decommissioning waste management.


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