Relevant bibliographies by topics / Metallic nuclear waste

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  1. Journal articles

Academic literature on the topic 'Metallic nuclear waste'

Author: Grafiati
Published: 19 April 2025

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Journal articles on the topic "Metallic nuclear waste"

1

Stoulil, J., and D. Dobrev. "Microbial corrosion of metallic materials in a deep nuclear-waste repository." Koroze a ochrana materialu 60, no. 2 (2016): 59–67. http://dx.doi.org/10.1515/kom-2016-0010.

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AbstractThe study summarises current knowledge on microbial corrosion in a deep nuclear-waste repository. The first part evaluates the general impact of microbial activity on corrosion mechanisms. Especially, the impact of microbial metabolism on the environment and the impact of biofilms on the surface of structure materials were evaluated. The next part focuses on microbial corrosion in a deep nuclear-waste repository. The study aims to suggest the development of the repository environment and in that respect the viability of bacteria, depending on the probable conditions of the environment,
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2

Dietz, N. L., and D. D. Keiser. "TEM Analysis of Corrosion Products From a Radioactive Stainless Steel-based Alloy." Microscopy and Microanalysis 6, S2 (2000): 368–69. http://dx.doi.org/10.1017/s1431927600034334.

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Argonne National Laboratory has developed an electrometallurgical treatment process for metallic spent nuclear fuel from the Experimental Breeder Reactor-II. This process stabilizes metallic sodium and separates usable uranium from fission products and transuranic elements that are contained in the fuel. The fission products and other waste constituents are placed into two waste forms: a ceramic waste form that contains the transuranic elements and active fission products such as Cs, Sr, I and the rare earth elements, and a metal alloy waste form composed primarily of stainless steel (SS), fro
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3

Janney, D. E., and D. D. Keiser. "Actinides in metallic waste from electrometallurgical treatment of spent nuclear fuel." JOM 55, no. 9 (2003): 59–60. http://dx.doi.org/10.1007/s11837-003-0032-z.

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4

Holt, Erika, Maria Oksa, Matti Nieminen, et al. "Predisposal conditioning, treatment, and performance assessment of radioactive waste streams." EPJ Nuclear Sciences & Technologies 8 (2022): 40. http://dx.doi.org/10.1051/epjn/2022036.

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Before the final disposal of radioactive wastes, various processes can be implemented to optimise the waste form. This can include different chemical and physical treatments, such as thermal treatment for waste reduction, waste conditioning for homogenisation and waste immobilisation for stabilisation prior to packaging and interim storage. Ensuring the durability and safety of the waste matrices and packages through performance and condition assessment is important for waste owners, waste management organisations, regulators and wider stakeholder communities. Technical achievements and lesson
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5

Barton, Daniel N. T., Thomas Johnson, Anne Callow, et al. "A review of contamination of metallic surfaces within aqueous nuclear waste streams." Progress in Nuclear Energy 159 (May 2023): 104637. http://dx.doi.org/10.1016/j.pnucene.2023.104637.

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6

Moiseenko, V., and S. Chernitskiy. "Nuclear Fuel Cycle with Minimized Waste." Nuclear and Radiation Safety, no. 1(81) (March 12, 2019): 30–35. http://dx.doi.org/10.32918/nrs.2019.1(81).05.

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A uranium-based nuclear fuel and fuel cycle are proposed for energy production. The fuel composition is chosen so that during reactor operation the amount of each transuranic component remains unchanged since the production rate and nuclear reaction rate are balanced. In such a ‘balanced’ fuel only uranium-238 content has a tendency to decrease and, to be kept constant, must be sustained by continuous supply. The major fissionable component of the fuel is plutonium is chosen. This makes it possible to abandon the use of uranium-235, whose reserves are quickly exhausted. The spent nuclear fuel
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7

Janney, Dawn E. "Host phases for actinides in simulated metallic waste forms." Journal of Nuclear Materials 323, no. 1 (2003): 81–92. http://dx.doi.org/10.1016/j.jnucmat.2003.08.032.

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8

Rodríguez, Martín A. "Anticipated Degradation Modes of Metallic Engineered Barriers for High-Level Nuclear Waste Repositories." JOM 66, no. 3 (2014): 503–25. http://dx.doi.org/10.1007/s11837-014-0873-7.

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9

Janney, D. E. "Incorporation of Actinide Elements into Iron-Zirconium Intermetallic Phases in Metallic Waste Forms for High-Level Nuclear Waste." Microscopy and Microanalysis 8, S02 (2002): 1310–11. http://dx.doi.org/10.1017/s1431927602104983.

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10

Pavliuk, Alexander O., Evgeniy V. Bespala, Sergey G. Kotlyarevskiy, Ivan Yu Novoselov, and Veleriy N. Kotov. "Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite." Science and Technology of Nuclear Installations 2022 (January 30, 2022): 1–13. http://dx.doi.org/10.1155/2022/2957310.

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The article is dedicated to the safety assessment of mixed storage of irradiated graphite and other types of radioactive waste accumulated during the operation of uranium-graphite reactors. The analysis of heat release processes inside storages containing irradiated nuclear graphite, representing a potential hazard due to the possible heating and, accordingly, the release of long-lived radionuclides during oxidation was carried out. The following factors were considered as the main factors that can lead to an increase in the temperature inside the storage facility: corrosion of metallic radioa
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