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

Kiegiel, Katarzyna; Herdzik-Koniecko, Irena; Fuks, L.; Zakrzewska-Kołtuniewicz, Grażyna

doi:10.3390/en15031099

Cited by 8 publications

(8 citation statements)

References 44 publications

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“…Applying the Rietveld full-profile method to evaluate the contributions of the two phases in the structure of the investigated samples, it was found that the phase ratio is PyC:SiC = 73.3:26.7. Analysis of the crystal lattice parameters and volume for the SiC phase made it possible to establish that the integral porosity value of the examined samples is 1.61%, at a phase density of 3.134 g/cm 3 . The degree of crystallinity of the ceramic layer of silicon carbide is more than 95%, which indicates a high degree of structural ordering.…”

Section: Resultsmentioning

confidence: 99%

“…It was found that, in the initial state, the sphere surface has a developed structure consisting of fine-grained inclusions located on the surface with a high proportion of uniformity. Using the method of X-ray phase analysis, it was found that for the SiC phase the value of integral porosity of the studied samples is 1.61%, with a phase density of 3.134 g/cm 3 . The degree of crystallinity of the ceramic layer of silicon carbide is more than 95%, which indicates a high degree of structural ordering.…”

Section: Discussionmentioning

confidence: 97%

“…This study is motivated by the increase in energy consumption and the efforts underway to search for alternative energy sources, including active studies in the field of nuclear and thermonuclear energy. In Kazakhstan, in recent years, new materials for future nuclear and nuclear fuel cycle facilities have been widely studied [ 1 , 2 , 3 , 4 ]; reactor [ 5 , 6 , 7 , 8 , 9 , 10 , 11 , 12 , 13 , 14 , 15 , 16 ] and out-of-pile [ 17 , 18 , 19 ] experiments simulating their operating conditions have been conducted. One area of such work is corrosion testing of materials for the high-temperature gas reactor (HTGR), a Generation IV in the early design stage [ 20 , 21 , 22 , 23 ].…”

Section: Introductionmentioning

confidence: 99%

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Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

et al. 2022

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The purpose of this work is to characterize the morphological, structural, and strength properties of model prototypes of new-generation TRi-structural ISOtropic particle fuel (TRISO) designed for Generation IV high-temperature gas reactors (HTGR-type). The choice of model structures consisting of inner pyrolytic carbon (I-PyC), silicon carbide (SiC), and outer pyrolytic carbon (O-PyC) as objects of research is motivated by their potential use in creating a new generation of fuel for high-temperature nuclear reactors. To fully assess their full functional value, it is necessary to understand the mechanisms of resistance to external influences, including mechanical, as in the process of operation there may be external factors associated with deformation and leading to the destruction of the surface of fuel structures, which will critically affect the service life. The objective of these studies is to obtain new data on the fuel properties, as well as their resistance to external influences arising from mechanical friction. Such studies are necessary for further tests of this fuel on corrosion and irradiation resistance, as closely as possible to real conditions in the reactor. The research revealed that the study samples have a high degree of resistance to external mechanical influences, due to the high strength of the upper layer consisting of pyrolytic carbon. The presented results of the radiation resistance of TRISO fuel testify to the high resistance of the near-surface layer to high-dose irradiation.

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Section: Resultsmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 97%

Section: Introductionmentioning

confidence: 99%

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Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

et al. 2022

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“…Для решения всех вышеуказанных требований, как правило, в качестве основы инертных матриц используют тугоплавкие оксидные соединения, а также их смеси, что позволяет совместить положительные качества оксидных соединений и получить материал, обладающий большими перспективами использования в качестве дисперсного ядерного топлива [8][9][10].…”

Section: Introductionunclassified

Study of Phase Formation Processes in Cer-Cer Type Inert Matrices Based on Oxide Compounds

Kenzhina

Shaimerdenov²,

Tolenova

et al. 2022

jour

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The purpose of this work is to study the processes of phase formation in the samples (1-x)ZrO2 – xAl2O3 ceramics depending on the variation of the oxide components, as well as to establish changes in the structural parameters and degree of crystallinity. The choice of zirconium and aluminum oxides as the basis for cer-cer inert matrices for nuclear fuel is due to their physical, chemical, structural and mechanical properties, the combination of which will produce a new type of ceramics with great potential in the field of nuclear fuel. These oxide compounds have high thermal stability and resistance to high temperatures, which also allows their use as a basis for disperse nuclear fuel for new-generation hightemperature nuclear reactors. The method of mechanochemical milling followed by thermal annealing was chosen to obtain ceramics based on oxide compounds. The choice of grinding conditions, as well as the subsequent thermal annealing was chosen to initiate the processes of phase transformations and structural changes as a result of thermal influence and partial relaxation of the deformation distortions and metastable formations initiated during grinding. The X-ray diffraction method was chosen as the main method to study the processes of phase transformation and structural changes. During the studies it was found that the addition of aluminum oxide leads to the structural ordering of the main monocline phase ZrO2, as well as the formation of solid solutions of substitution and introduction. At equal concentrations of the oxide components using the method of X-ray phase analysis was established polymorphic phase transformation in zirconium dioxide, the presence of which indicates the processes of phase transformation arising from the addition of zirconium oxide and changes in the phase formation processes.

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“…Kiegiel et al [2] present the final part of the HTGR fuel cycle. The review presents many methods that could be employed to ensure the sustainable, feasible management and longterm storage of HTGR nuclear waste in order to protect the environment and society.…”

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confidence: 99%

Storage and Disposal Options for Nuclear Waste

Kiegiel

2022

Energies

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

Cited by 8 publications

References 44 publications

Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

Study of Phase Formation Processes in Cer-Cer Type Inert Matrices Based on Oxide Compounds

Storage and Disposal Options for Nuclear Waste

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