TY  - JOUR
AU  - Plećaš, Ilija B.
AU  - Arbutina, D.
PY  - 2013
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/5728
AB  - Two fundamental concerns must be addressed when attempting to isolate low-level waste in a disposal facility on land. The first concern is isolating the waste from water, or hydrologic isolation. The second is preventing movement of the radionuclides out of the disposal facility, or radionuclide migration. Particularly, we have investigated here the latter modified scenario. To assess the safety for disposal of radioactive waste-concrete composition, the leakage of Co-60 from a waste composite into a surrounding fluid has been studied. Leakage tests were carried out by original method, developed in Vinca Institute. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using 3 methods based on theoretical equations. These are: the diffusion equation for a plane source, an equation for diffusion coupled to a first-order equation, and an empirical method employing a polynomial equation. The results presented in this paper are from a 35-year mortar and concrete testing project that will influence the design choices for radioactive waste packaging for a future Serbian radioactive waste disposal center.
T2  - Journal of Environmental Protection and Ecology
T1  - Modelling of Transport Phenomena in Concrete Porous Media
VL  - 14
IS  - 3
SP  - 1059
EP  - 1065
UR  - https://hdl.handle.net/21.15107/rcub_vinar_5728
ER  - 

@article{
author = "Plećaš, Ilija B. and Arbutina, D.",
year = "2013",
abstract = "Two fundamental concerns must be addressed when attempting to isolate low-level waste in a disposal facility on land. The first concern is isolating the waste from water, or hydrologic isolation. The second is preventing movement of the radionuclides out of the disposal facility, or radionuclide migration. Particularly, we have investigated here the latter modified scenario. To assess the safety for disposal of radioactive waste-concrete composition, the leakage of Co-60 from a waste composite into a surrounding fluid has been studied. Leakage tests were carried out by original method, developed in Vinca Institute. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using 3 methods based on theoretical equations. These are: the diffusion equation for a plane source, an equation for diffusion coupled to a first-order equation, and an empirical method employing a polynomial equation. The results presented in this paper are from a 35-year mortar and concrete testing project that will influence the design choices for radioactive waste packaging for a future Serbian radioactive waste disposal center.",
journal = "Journal of Environmental Protection and Ecology",
title = "Modelling of Transport Phenomena in Concrete Porous Media",
volume = "14",
number = "3",
pages = "1059-1065",
url = "https://hdl.handle.net/21.15107/rcub_vinar_5728"
}

Plećaš, I. B.,& Arbutina, D.. (2013). Modelling of Transport Phenomena in Concrete Porous Media. in Journal of Environmental Protection and Ecology, 14(3), 1059-1065.
https://hdl.handle.net/21.15107/rcub_vinar_5728

Plećaš IB, Arbutina D. Modelling of Transport Phenomena in Concrete Porous Media. in Journal of Environmental Protection and Ecology. 2013;14(3):1059-1065.
https://hdl.handle.net/21.15107/rcub_vinar_5728 .

Plećaš, Ilija B., Arbutina, D., "Modelling of Transport Phenomena in Concrete Porous Media" in Journal of Environmental Protection and Ecology, 14, no. 3 (2013):1059-1065,
https://hdl.handle.net/21.15107/rcub_vinar_5728 .

TY  - JOUR
AU  - Sekulić, Danijela R.
AU  - Stevanović, M. M.
PY  - 2011
UR  - https://vinar.vin.bg.ac.rs/handle/123456789/4331
AB  - Hardness and Youngs modulus of the matrix and fibers in carbon/epoxy gamma irradiated and annealed composites were investigated using nanoindentation technique. The Vickers microhardness of the tested composites after irradiation and annealing was studied, as well. Gamma irradiation to various doses (5-27 MGy) of UDC plates, were followed by thermal treatments of irradiated coupons at 180 and 250 degrees C, in vacuum. The measured changes of nano and micro properties were correlated to glass transition temperatures, as well as the delamination toughness changes, determined earlier on the same material. The established irradiation and annealing effects on nanoindentation properties and Vickers mocrohardness were analyzed as a function of the matrix plasticity change. An attempt was made to assess the contribution of chain scission mechanism and the change in plasticity mechanism on the property changes from irradiation and subsequent thermal treatments. (C) 2011 Elsevier B.V. All rights reserved.
T2  - Journal of Nuclear Materials
T1  - Effects of gamma irradiation and post-irradiation annealing on carbon/epoxy UDC properties deduced by methods of local loading
VL  - 412
IS  - 1
SP  - 190
EP  - 194
DO  - 10.1016/j.jnucmat.2011.01.125
ER  - 

@article{
author = "Sekulić, Danijela R. and Stevanović, M. M.",
year = "2011",
abstract = "Hardness and Youngs modulus of the matrix and fibers in carbon/epoxy gamma irradiated and annealed composites were investigated using nanoindentation technique. The Vickers microhardness of the tested composites after irradiation and annealing was studied, as well. Gamma irradiation to various doses (5-27 MGy) of UDC plates, were followed by thermal treatments of irradiated coupons at 180 and 250 degrees C, in vacuum. The measured changes of nano and micro properties were correlated to glass transition temperatures, as well as the delamination toughness changes, determined earlier on the same material. The established irradiation and annealing effects on nanoindentation properties and Vickers mocrohardness were analyzed as a function of the matrix plasticity change. An attempt was made to assess the contribution of chain scission mechanism and the change in plasticity mechanism on the property changes from irradiation and subsequent thermal treatments. (C) 2011 Elsevier B.V. All rights reserved.",
journal = "Journal of Nuclear Materials",
title = "Effects of gamma irradiation and post-irradiation annealing on carbon/epoxy UDC properties deduced by methods of local loading",
volume = "412",
number = "1",
pages = "190-194",
doi = "10.1016/j.jnucmat.2011.01.125"
}

Sekulić, D. R.,& Stevanović, M. M.. (2011). Effects of gamma irradiation and post-irradiation annealing on carbon/epoxy UDC properties deduced by methods of local loading. in Journal of Nuclear Materials, 412(1), 190-194.
https://doi.org/10.1016/j.jnucmat.2011.01.125

Sekulić DR, Stevanović MM. Effects of gamma irradiation and post-irradiation annealing on carbon/epoxy UDC properties deduced by methods of local loading. in Journal of Nuclear Materials. 2011;412(1):190-194.
doi:10.1016/j.jnucmat.2011.01.125 .

Sekulić, Danijela R., Stevanović, M. M., "Effects of gamma irradiation and post-irradiation annealing on carbon/epoxy UDC properties deduced by methods of local loading" in Journal of Nuclear Materials, 412, no. 1 (2011):190-194,
https://doi.org/10.1016/j.jnucmat.2011.01.125 . .