Innovative and conventional materials and designs of nuclear cementitious systems in radioactive waste management

Varlakov, A. P.; Zherebtsov, A. A.

doi:10.1016/b978-0-12-818328-1.00004-6

Cited by 6 publications

(2 citation statements)

References 19 publications

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“…the gradual transition from a liquid colloidal suspension to a solid water-saturated gel (hydrogel), able to seal fractured materials and to embed loose particulates. Unlike cementitious grouts already in use for nuclear waste immobilisation (both conventional and novel highpenetration grouts, Varlakov and Zherebtsov, 2021), CS hydrogels can be easily excavated without producing fine particulates. CS hydrogels can also provide radiation shielding thanks to their high water content (typically >60% by mass), and have been shown to enhance the immobilisation capacity of radioactively contaminated soils and waste materials (Bots, et al, 2020).…”

Section: Introductionmentioning

confidence: 99%

Colloidal silica as a grouting material for the temporary encapsulation of heat-generating radioactive waste during removal and transport operations: A proof of concept

2023

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Hazardous nuclear waste is produced at all stages during the nuclear fuel cycle. The removal operations of nuclear waste from nuclear reactors and/or storage facilities, such as spent fuel pools and storage silos, pose a hazard for the workforce and the environment, due to the potential release of radioactive particulates, and loss of radioactive debris. The development of innovative techniques to address this issue is desirable. A potential technology to inhibit particulate release during nuclear waste removal and transport operations is colloidal silica grouting. Colloidal silica is an aqueous suspension of silica (SiO2) nanoparticles, able to provide immobilisation of particulates within a hydrogel matrix. In this study, an experimental investigation was carried out to simulate colloidal silica grouting operations around objects at temperatures of 60°C and 120°C, to simulate radioactive waste in standard storage conditions, and during loss of cooling/loss of coolant accident scenarios. The results of the experimental campaign confirm the suitability of colloidal silica to safely remove and transport heat-generating radioactive waste. Critical parameters for designing the silica grout mix, in order to optimise the performance of the hydrogel upon exposure to temperature in different scenarios, are identified and discussed.

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Section: Introductionmentioning

confidence: 99%

Colloidal silica as a grouting material for the temporary encapsulation of heat-generating radioactive waste during removal and transport operations: A proof of concept

2023

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“…В работах представлены результаты исследований свойств цементных компаундов и технологических параметров для различных РАО, вяжущих материалов, добавок . Объектами анализа являлись солевые водные растворы, пульпы ионообменных материалов, осадки, илы, жидкие органические радиоактивные отходы, зола от сжигания горючих отходов и другие жидкие и твердые РАО (ЖРО, ТРО) [1][2][3][4][5][6] .…”

Section: Introductionunclassified

Radioactive waste cementation via the in-container hot pressing method

Varlakov¹,

Zherebtsov²,

Germanov³

et al. 2022

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The paper explores mechanical, physical, chemical and structural properties of cement compounds based on blastfurnace slag produced in metal containers using the hot isostatic pressing (HIP) method. The study allowed to evaluate the radiation resistance of cement compounds under the influence of ionizing radiation up to an absorbed dose of 109 Gy and 1019 alpha-dispersion/g. The tests confirmed that the matrices complied with the established regulatory requirements. It was demonstrated that cement compound synthesis based on the HIP method provided matrices with enhanced physical and chemical characteristics. It was also shown that under radiation exposure, cement compounds containing high-level waste simulators retained their properties and structure.

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Evaluation of disposal stability of cement waste forms mixed with concentrated liquid waste for efficient treatment of AUC process waste

Shon

Lee²,

Kim³

et al. 2022

J Radioanal Nucl Chem

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Innovative and conventional materials and designs of nuclear cementitious systems in radioactive waste management

Cited by 6 publications

References 19 publications

Colloidal silica as a grouting material for the temporary encapsulation of heat-generating radioactive waste during removal and transport operations: A proof of concept

Colloidal silica as a grouting material for the temporary encapsulation of heat-generating radioactive waste during removal and transport operations: A proof of concept

Radioactive waste cementation via the in-container hot pressing method

Evaluation of disposal stability of cement waste forms mixed with concentrated liquid waste for efficient treatment of AUC process waste

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