HTR Fuel Waste Management: TRISO separation and acid-graphite intercalation compounds preparation

Guittonneau, Fabrice; Abdelouas, Abdesselam; Grambow, Bernd

doi:10.1016/j.jnucmat.2010.09.026

Cited by 11 publications

(3 citation statements)

References 33 publications

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“…The detached compacts or TRISO particles can be directed to the storage or can be reprocessed for U and Pu recovery. Guittonneau et al [49] proposed a method which allows the total degradation of graphite blocks and the separation of TRISO particles while maintaining their cohesion. The method was based on the intercalation of sulfuric acid into graphite layers to separate the grains.…”

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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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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“…Nitronium results from a reaction of a mixture of sulfuric acid (95%) and nitric acid (69%) at 200°C. It causes damage to the outer layers of TRISO particles and can reach the SiC layer through a corrosion of the outer pyrolitic carbon (OPYC) . Therefore, the authors proposed an alternative solution of a moderate oxidant, produced from a reaction of sulfuric acid with hydrogen peroxide at a room temperature.…”

Section: Introductionmentioning

confidence: 99%

“…It causes damage to the outer layers of TRISO particles and can reach the SiC layer through a corrosion of the outer pyrolitic carbon (OPYC). 4 Therefore, the authors proposed an alternative solution of a moderate oxidant, produced from a reaction of sulfuric acid with hydrogen peroxide at a room temperature. The resulting TRISO particles have a different thickness of SiC layer.…”

Section: Introductionmentioning

confidence: 99%

Interaction of Embedded Tri‐Isotropic Fuel Particles with Melt of Alkaline Borosilicate Glass

Hamodi

Lowe

Abram

2012

Int J of Appl Glass Sci

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A silicon carbide (SiC) layer is an outer‐coated layer of spent tri‐isotropic (TRISO) fuel particles and it is known to be a pressure vessel for retaining fission products, and preventing contamination in the primary circuit of a nuclear reactor. The goal of this article is to elucidate the chemical bonding and an interface formation of an alkaline borosilicate glass (ABG) with the coating layer of TRISO fuel particles. Particular emphasis is placed on the analysis of the intermediate chemical phase at the interface SiC/glass as a function of the material impurity and thickness of the SiC layer. The findings provide valuable information regarding the restriction parameters of immobilisation TRISO particles in glass. The interaction between the glass and SiC caused a total destruction of a thin SiC layer (10 μm), a random partial interaction to a thick SiC layer (40 μm) and formation of bubbles (CO2, CO) to an inner pyrolitic carbon (IPYC). The Raman spectroscopy analysis revealed that the interaction of ABG with the SiC layer occurred at a point, where a low excess of carbon was co‐deposited during chemical vapour deposition process. The interaction resulted in a formation of a mono‐crystal SiC, dispersed in vitreous silica as a crystalline inclusion.

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Preparation of sulfur-doped graphite by solid-state microwave method: The effect of reaction conditions on the sulfur-doping process

et al. 2019

Chemical Physics Letters

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HTR Fuel Waste Management: TRISO separation and acid-graphite intercalation compounds preparation

Cited by 11 publications

References 33 publications

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

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

Interaction of Embedded Tri‐Isotropic Fuel Particles with Melt of Alkaline Borosilicate Glass

Preparation of sulfur-doped graphite by solid-state microwave method: The effect of reaction conditions on the sulfur-doping process

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