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This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License
Article
Author(s)
Vanessa Mota Vieira and Clédola Cássia Oliveira de Tello
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DOI:10.17265/2162-5263/2016.11.005
Affiliation(s)
Nuclear Technology Development Center (CDTN/CNEN), Department of Radioactive Waste Belo Horizonte, Pampulha Av. Presidente Antônio Carlos, 6.627, 31270-901, MG, Brazil.
ABSTRACT
The Brazilian repository is being planned to be a near-surface one. In Brazil, the low and intermediate
level radioactive wastes are immobilized using cement and bitumen for nuclear plant
Angra 1 and Angra 2, respectively. The major problems due to the disposal of bituminized
wastes in repositories are swelling of the waste products and their degradation
in the long term. To accommodate the swelling of the bituminized wastes, the drums
are filled up to 70-90% of their volume, which reduces the structural the repository
stability and the disposal availability. Countries, which use bitumen in the solidification
of NPP’s radioactive waste and
have near-surface repositories, need to immobilize this bituminized waste within
other drums containing cement pastes or mortars to disposal them. This study aims
to evaluate the properties of bitumen, cement pastes and mortars to be used in the
encapsulation of bituminized wastes. The formulations of two pastes and two mortars
were selected for the pilot scale tests. The laboratory and pilot scales results
were very similar, indicating that any of these formulations could be used. However, the better formulation
will be chosen after the leaching test results, because it is an essential parameter
in the long-term repository performance.
KEYWORDS
Radioactive wastes, bitumen, cement pastes, mortars.
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