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Dezerald L, Kohanoff JJ, Correa AA, Caro A, Pellenq RJM, Ulm FJ, Saúl A. Cement As a Waste Form for Nuclear Fission Products: The Case of (90)Sr and Its Daughters. ENVIRONMENTAL SCIENCE & TECHNOLOGY 2015; 49:13676-13683. [PMID: 26513644 DOI: 10.1021/acs.est.5b02609] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/05/2023]
Abstract
One of the main challenges faced by the nuclear industry is the long-term confinement of nuclear waste. Because it is inexpensive and easy to manufacture, cement is the material of choice to store large volumes of radioactive materials, in particular the low-level medium-lived fission products. It is therefore of utmost importance to assess the chemical and structural stability of cement containing radioactive species. Here, we use ab initio calculations based on density functional theory (DFT) to study the effects of (90)Sr insertion and decay in C-S-H (calcium-silicate-hydrate) in order to test the ability of cement to trap and hold this radioactive fission product and to investigate the consequences of its β-decay on the cement paste structure. We show that (90)Sr is stable when it substitutes the Ca(2+) ions in C-S-H, and so is its daughter nucleus (90)Y after β-decay. Interestingly, (90)Zr, daughter of (90)Y and final product in the decay sequence, is found to be unstable compared to the bulk phase of the element at zero K but stable when compared to the solvated ion in water. Therefore, cement appears as a suitable waste form for (90)Sr storage.
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Affiliation(s)
- Lucile Dezerald
- Department of Civil and Environmental Engineering, Massachusetts Institute of Technology , Cambridge, Massachusetts 02139, United States
- MultiScale Material Science for Energy and Environment, UMI 3466 CNRS-MIT, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139, United States
| | - Jorge J Kohanoff
- Atomistic Simulation Centre, Queen's University Belfast , Belfast BT7 1NN, United Kingdom
| | - Alfredo A Correa
- Condensed Matter and Materials Division, Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory , Livermore, California 94550, United States
| | - Alfredo Caro
- Los Alamos National Laboratory , Los Alamos, New Mexico 87545, United States
| | - Roland J-M Pellenq
- Department of Civil and Environmental Engineering, Massachusetts Institute of Technology , Cambridge, Massachusetts 02139, United States
- MultiScale Material Science for Energy and Environment, UMI 3466 CNRS-MIT, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139, United States
- Aix-Marseille University, CINaM-CNRS UMR 7325 Campus de Luminy, 13288 Marseille cedex 9, France
| | - Franz J Ulm
- Department of Civil and Environmental Engineering, Massachusetts Institute of Technology , Cambridge, Massachusetts 02139, United States
- MultiScale Material Science for Energy and Environment, UMI 3466 CNRS-MIT, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139, United States
| | - Andrés Saúl
- Department of Civil and Environmental Engineering, Massachusetts Institute of Technology , Cambridge, Massachusetts 02139, United States
- MultiScale Material Science for Energy and Environment, UMI 3466 CNRS-MIT, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139, United States
- Aix-Marseille University, CINaM-CNRS UMR 7325 Campus de Luminy, 13288 Marseille cedex 9, France
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Abstract
AbstractThis review describes nuclear waste forms for high-level waste (HLW), that is, glasses, ceramics, and glass-ceramics, as well as for low- and intermediate-level waste (LILW), that is, cement, bitumen, glass, glassy slags, and ceramics. Ceramic waste forms have the highest chemical durability and radiation resistance, and are recommended for HLW and actinide (ACT) immobilization. Most radiation-resistant materials are based on phases with a fluorite-related structure (cubic zirconia-based solid solutions, pyrochlore, zirconolite, murataite). Glass is also a suitable matrix for HLW containing fission and corrosion products, and process contaminants such as Na salts. Within the framework of the HLW partitioning concept providing separation of short-lived (Cs, Sr) and long-lived (rare earth element-ACT) fractions, glass may be used for immobilization of the Cs-Sr-bearing fraction, whereas the rare earth-ACT fraction may be incorporated in ceramics. Glass-based materials or clay-based ceramics are the most promising LILW forms, but cement and bitumen may also be applied as matrices for low-level wastes (LLW).
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Affiliation(s)
| | | | - Reto Gieré
- Institut für Mineralogie, Petrologie und Geochemie, Universität Freiburg
Albertstrasse 23b, D-79104 Freiburg, Germany
| | - Gregory R. Lumpkin
- ANSTO, Materials Division
Menai, NSW 2234, Australia
Cambridge Centre for Ceramic Immobilisation, Department of Earth Sciences, University of Cambridge
Downing Street, Cambridge, CB2 3EQ, UK
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