Immobilization of inert TRISO-coated fuel in glass for geological disposal

Abdelouas, Abdesselam; Noirault, Samuel; Grambow, Bernd

doi:10.1016/j.jnucmat.2006.04.015

Cited by 12 publications

(10 citation statements)

References 17 publications

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“…In order to reduce waste volume, fuel compacts are generally pulverized to separate the low level waste graphite from high level waste fuel particles. These particles are then placed in a different matrix, such as glass or ceramic, for a long term disposal [3]. In our research, the process of intercalation of TRISO particles from its graphite matrix caused damage to the outer coating of TRISO particles and released fission products from the kernel.…”

Section: Introductionmentioning

confidence: 90%

“…Then, the die was removed and cooled to room temperature. The pellets were removed from the die and annealed for 1 h at 773 K. The densities of the waste forms were measured by Archimedes method and were 2.19 g/cm 3 and 1.81 g/cm 3 for ABG and GGC respectively, considering that the density of TRISO particles was 4.6 g/cm 3 . The produced GGC matrix is shown in Fig.…”

Section: Sample Preparationmentioning

confidence: 99%

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The chemical durability of glass and graphite–glass composite doped with cesium oxide

Hamodi

Abram

Lowe

et al. 2013

Journal of Nuclear Materials

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a b s t r a c tThe role of temperature in determining the chemical stability of a waste form, as well as its leach rate, is very complex. This is because the dissolution kinetics is dependent both on temperature and possibility of different rate-controlling mechanisms that appear at different temperature regions. The chemical durability of Alumina-Borosilicate Glass (ABG) and Glass-Graphite Composite (GGC), bearing Tristructural Isotropic (TRISO) fuel particles impregnated with cesium oxide, were compared using a static leach test. The purpose of this study is to examine the chemical durability of glass-graphite composite to encapsulate coated fuel particles, and as a possible alternative for recycling of irradiated graphite. The test was based on the ASTM C1220-98 methodology, where the leaching condition was set at a temperature varying from 298 K to 363 K for 28 days. The release of cesium from ABG was in the permissible limit and followed the Arrhenius's law of a surface controlled reaction; its activation energy (E a ) was 65.6 ± 0.5 kJ/mol. Similar values of Ea were obtained for Boron (64.3 ± 0.5) and Silicon (69.6 ± 0.5 kJ/ mol) as the main glass network formers. In contrast, the dissolution mechanism of cesium from GGC was a rapid release, with increasing temperature, and the activation energy of Cs (91.0 ± 5 kJ/mol) did not follow any model related to carbon kinetic dissolution in water. Microstructure analysis confirmed the formation of Crystobalite SiO 2 as a gel layer and Cs +1 valence state on the ABG surface.

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Section: Introductionmentioning

confidence: 90%

Section: Sample Preparationmentioning

confidence: 99%

The chemical durability of glass and graphite–glass composite doped with cesium oxide

Hamodi

Abram

Lowe

et al. 2013

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…There is only one research done on direct vitrification of inert TRISO particles in borosilicate glass. 8 The authors of that research reported that direct melting was unsuccessful due to a floatation of particles over the molten glass. All coated layers were oxidized and diminished and then, the kernel sank to the bottom of the glass plenum.…”

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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“…Furthermore this is not just a legacy issue, as many new reactors designs include the use of graphite. Reactor designs such as the Very High Temperature Reactor (VHTR) and Pebble Bed Modular Reactor (PBMR) utilise graphite encapsulated fuel particles in their design, instead of more conventional fuel rods [4]. If these designs go forward to be used in future commercial power stations then it is clear that a route for the immobilisation and consequent disposal of irradiated graphite will be required.…”

Section: Introductionmentioning

confidence: 99%

The synthesis of graphite–glass composites intended for the immobilisation of waste irradiated graphite

McGann

Ojovan

2011

Journal of Nuclear Materials

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Immobilization of inert TRISO-coated fuel in glass for geological disposal

Cited by 12 publications

References 17 publications

The chemical durability of glass and graphite–glass composite doped with cesium oxide

The chemical durability of glass and graphite–glass composite doped with cesium oxide

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

The synthesis of graphite–glass composites intended for the immobilisation of waste irradiated graphite

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