Methods of Emergency Heat Removal from Pools and Storages of Spent Fuel of Nuclear Power Plants

Karyakin, Yu. E.; Peich, N. N.; Pletnev, A. A.; Fedorovich, E. D.

doi:10.1007/s10891-019-01963-1

Cited by 2 publications

(1 citation statement)

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“…In extreme scenarios (e.g. loss of cooling/loss of coolant accidents), the radioactive waste may be found at significantly higher temperatures, exceeding 100 °C (Karyakin et al, 2019).…”

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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“…In extreme scenarios (e.g. loss of cooling/loss of coolant accidents), the radioactive waste may be found at significantly higher temperatures, exceeding 100 °C (Karyakin et al, 2019).…”

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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Digital technologies in nuclear power plant probabilistic safety assessment

Aksenov

Egorov

2020

IOP Conf. Ser.: Mater. Sci. Eng.

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The ability of systems, structures and components that provide ultimate heat sink, to perform their functions and to ensure the safety of the nuclear power plant with VVER-1200 reactor in the events of external influences that entail the loss of ultimate heat sink is subject of the study. Necessity of consideration of mentioned events was demonstrated by last events occurred on NPPs worldwide in particular in Fukushima-Daiichi accident. Probabilistic model was developed implementing modern methods for assessment of probabilistic safety values using digital software RiskSpectrumPSA. Calculated probabilistic safety values confirm chosen design solutions and possibility of probabilistic safety assessment application for similar tasks.

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Methods of Emergency Heat Removal from Pools and Storages of Spent Fuel of Nuclear Power Plants

Cited by 2 publications

References 0 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

Digital technologies in nuclear power plant probabilistic safety assessment

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