Modeling spent TRISO fuel for geological disposal: corrosion and failure under oxidizing conditions in the presence of water

Peterson, Joshua L.; Dunzik-Gougar, Mary Lou

doi:10.1016/j.pnucene.2010.12.003

Cited by 11 publications

(5 citation statements)

References 1 publication

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“…Geological disposal is currently considered as the technically feasible and safe manner for long-term management of nuclear waste. The engineered system of the repository is designed to complement the natural geological barrier and to provide primary physical-chemical nuclear waste forms [3,4]. However, high temperature, high pressure, radiation and water infiltration may be encountered by nuclear waste forms after being placed in geological repositories [5].…”

Section: Introductionmentioning

confidence: 99%

Phase evolution and chemical durability of co-doped Gd2Zr2O7 ceramics for nuclear waste forms

Fan

Shu

et al. 2015

Ceramics International

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Section: Introductionmentioning

confidence: 99%

Phase evolution and chemical durability of co-doped Gd2Zr2O7 ceramics for nuclear waste forms

Fan

Shu

et al. 2015

Ceramics International

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“…The modelling and analysing of decomposition rates of the spent fuel from HTGR have been done by Peterson and Dunzik-Gougar [50] in relation to planned permanent geological disposal. Their aim was to find the parameters that would have the most impact on broad behaviour of the fuel.…”

Section: Triso Spent Fuel Managementmentioning

confidence: 99%

Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art

et al. 2022

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In light of the increasing demand for energy sources in the world and the need to meet climate goals set by countries, there is growing global interest in high temperature gas cooled reactors (HTGRs), especially as they are known to be inherently safe nuclear reactors. The safety of HTGRs results, among other, from the nature of the nuclear fuel used in them in the form of coated TRISO particles (tri-structural-isotropic) and the reduction of the total amount of radioactive waste generated. This paper reviews numerous methods used to ensure the sustainable, feasible management and long-term storage of HTGR nuclear waste for the protection of the environment and society. The types of waste generated in the HTGR cycle are presented as well as the methods of their characterization, which are important for long-time storage and final disposal. Two leading nuclear fuel cycle strategies, the once-through cycle (direct disposal or open cycle) and the twice-through cycle (recycling or partially closed cycle), are discussed also in relation to TRISO spent fuel. A short review of the possibilities of treatment of TRISO spent nuclear fuel from HTGR reactors is made.

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“…Recent studies on the corrosion rates of unirradiated and irradiated SiC in different simulated ground waters over a range of temperatures revealed no significant long-term effect of irradiation on corrosion behaviour [14]. The mechanisms and rates of corrosion for SiC in different aqueous media under conditions relevant to geologic repositories have also been reported [15], and indicated that the radiotoxicity of spent TRISO fuel is at least four orders of magnitude lower than for current spent light water reactor fuel.…”

Section: Eejp 4 2018mentioning

confidence: 99%

Physical-Mechanical Properties of γ-Irradiated SiC Ceramics for Radioactive Wastes Immobilization

Lobach

Sayenko

Shkuropatenko

et al. 2018

EEJP

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The interest in silicon carbide (SiC-based) ceramics and composites as matrix material for nuclear waste immobilization is grown up. Long-term chemical durability and radiation resistance of SiC are important factors for radionuclides immobilization. Advantages of SiC-based ceramics as structural materials in nuclear applications are the high-temperature properties, high density and reduced neutron activation. The use of radiation resistant materials is a strong requirement for safe and environmentally beneficial energy system. The SiC ceramics stability under irradiation for temperatures up to 1273 K is also very important for nuclear power applications. The SiC matrices doped by additives of Cr, Si were fabricated using High Speed Hot Pressing Method. Additives content was in the range from 0.5 to 3 wt %. Microstructural characteristics of silicon carbide ceramics were analyzed by X-ray diffraction (XRD), scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDX), and infra-red spectroscopy (IR) methods. The results of microcracking under indentation conditions were revealed the lack of cracks in the SiC ceramics with Cr additives before and after irradiation process. In addition, it was demonstrated that samples of SiC with alloying additives Cr and Si possess high mechanical parameters under γ-irradiation process. The strength of ceramics increases with the uniform and fine-grained structure formation. The modification of phase composition and mechanical properties of the SiC ceramics with Cr and Si additives under γ-irradiation were analyzed for further development of radiation resistant and matrix materials for radioactive wastes immobilization.

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Modeling spent TRISO fuel for geological disposal: corrosion and failure under oxidizing conditions in the presence of water

Cited by 11 publications

References 1 publication

Phase evolution and chemical durability of co-doped Gd2Zr2O7 ceramics for nuclear waste forms

Phase evolution and chemical durability of co-doped Gd2Zr2O7 ceramics for nuclear waste forms

Management of Radioactive Waste from HTGR Reactors including Spent TRISO Fuel—State of the Art

Physical-Mechanical Properties of γ-Irradiated SiC Ceramics for Radioactive Wastes Immobilization

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