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Technique for Characterization and Clearance of the Resin Waste from the Greek Research Reactor (GRR-1)

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Hellenic Nuclear Physics Society   

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Technique for Characterization and Clearance of the Resin Waste from the Greek Research Reactor (GRR-1) (EN)
Ntalla, E.
Savvidou, A.
info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
2019-04-01
The present work concerns the examination of management options for VLLW drums [1] with ion exchange resin waste from the Greek Research Reactor (GRR-1). According to the general clearance criterion [2, 3], after cementation, 75 % of the VLLW could be cleared and for the remaining 25 % the summation formula result is lower than 1.6. The proposed management option for the total amount of the VLLW resin is the spread of the cemented resin, before thickening, over the ground around the interim storage facilities, inside the controlled area, for pavement construction. Additionally, a quantity of the cemented waste will be used for preparation of blocks for quality and homogeneity examination of the waste form. (EN)
resin waste (EN)
clearance (EN)
waste cementation (EN)
Annual Symposium of the Hellenic Nuclear Physics Society
English
Hellenic Nuclear Physics Society (HNPS) (EN)
2654-0088
2654-007X
Annual Symposium of the Hellenic Nuclear Physics Society; Τόμ. 25 (2017): HNPS2017; 130-135 (EL)
HNPS Advances in Nuclear Physics; Vol. 25 (2017): HNPS2017; 130-135 (EN)
Πνευματική ιδιοκτησία (c) 2019 E. Ntalla, A. Savvidou (EL)
Hellenic Nuclear Physics Society
Annual Symposium of the Hellenic Nuclear Physics Society
Oral contributions



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