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Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
-
Ilija Plecas
und
Dalibor Arbutina
Veröffentlicht/Copyright:
12. Dezember 2014
Abstract
An optimization of concrete used for immobilization of radionuclides 60Co and 137Cs, is presented. A relatively simple mathematical model is given, which permits minimization of leach rate and permeability and maximization of compressive strength. An optimal solution, based on experimental data, is given. These results will be used for a future Serbian radioactive waste disposal center.
Acknowledgement
Work supported by the Ministry of Ministry of Education, Science and Technology Development of the Republic of Serbia (Project No III 43009).
Received: 2014-9-1
Accepted: 2014-10-7
Published Online: 2014-12-12
Published in Print: 2015-2-28
©2014 Walter de Gruyter Berlin/Boston
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Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
Schlagwörter für diesen Artikel
Immobilization;
cement;
mortar;
concrete;
radioactivity;
waste;
leaching;
permeability
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
