scholarly journals Study of migration of radioactive elements in clay layers during the burial of radioactive waste

2021 ◽  
Vol 82 (4) ◽  
pp. 138-147
Author(s):  
M. I. Zhumanova ◽  
◽  
M. S. Tungatarova ◽  
Keyword(s):  
Radioactive Waste ◽  
Soil Layer ◽  
Underground Water ◽  
Convective Transport ◽  
Radioactive Elements ◽  
Energy Agency ◽  
Enriched Uranium ◽  
Clay Layers ◽  
Geological Formations ◽  
Clay Barrier

In 2015, Kazakhstan and the International Atomic Energy Agency (IAEA) signed an agreement to host a low-enriched uranium bank in Ust-Kamenogorsk. In 2019, several batches of enriched uranium were delivered to Kazakhstan and the bank began operations at the Ulba Metallurgical Plant. When transporting and disposing of radioactive elements, there is a need to reduce this possibility by limiting the transfer of uranium from underground storage to underground water. Therefore, in this article, a study was conducted on the migration of radioactive elements in clay layers during the disposal of radioactive uranium waste. There are now many underground repositories (for some types of radioactive waste). These systems are based on different underground container structures for different geological formations. For underground repositories located in geological environments where enriched uranium can migrate, other system components must reduce this possibility by preventing or limiting uranium mobility. This work investigates the process of convective transport of radioactive elements, in a moist soil layer through the installation of an additional natural clay barrier layer, the migration of radioactive elements during safe disposal, the effect of diffusion and convection through the solid waste layer.

scholarly journals PREDICTION OF THE TECTONIC PROCESSES AT A SELECTED AREAS FOR DISPOSE RADIOACTIVE WASTE

2007 ◽  
Vol 1 ◽  
pp. 70
Author(s):  
Vladislav Morozov ◽  
Sergey Belov ◽  
Ilya Kolesnikov ◽  
Victor Tatarinov
Keyword(s):  
Radioactive Waste ◽  
Underground Water ◽  
Tectonic Block ◽  
Tectonic Processes ◽  
Time Space ◽  
Geodynamic Processes ◽  
Heated Debate ◽  
High Level ◽  
Geological Formations ◽  
Hlw Repository

The possibility of using deep geological formations to dispose of high-level radioactive waste (HLW) is a subject raising heated debate among scientists. In Russia, the idea of constructing HLW repository in the Niznekansky granitoid massif (NKM) in Krasnoyarsk area is widely discussed. To solve this problem we are elaborating a technology associated with time - space stability prediction of the geological environment, which is subject to geodynamic processes evolutionary effects. It is based on the prediction of isolation properties stability in a structural tectonic block of the Earth’s crust for a given time. The danger is in the possibility that the selected structural block may be broken by new tectonic faults or movements on a passive fault may be activated and thus underground water may penetrate to HLW containers. 

scholarly journals Tectonic Processes Modeling For High-Level Radioactive Waste Disposal

2015 ◽  
Vol 1 ◽  
pp. 9
Author(s):  
Vladislav Morozov ◽  
Victor Tatarinov ◽  
Ilya Kolesnikov ◽  
Alexander Kagan ◽  
Tatiana Tatarinova
Keyword(s):  
Radioactive Waste ◽  
Underground Water ◽  
Radioactive Waste Disposal ◽  
Tectonic Block ◽  
High Level Radioactive Waste ◽  
Time Space ◽  
Geodynamic Processes ◽  
Heated Debate ◽  
High Level ◽  
Geological Formations

The possibility of using deep geological formations to dispose of high-level radioactive waste (HLW) is a subject raising heated debate among scientists. In Russia, the idea of constructing HLW repository in the Niznekansky granitoid massif (NKM) in Krasnoyarsk area is widely discussed. To solve this problem we are elaborating a technology associated with time – space stability prediction of the geological environment, which is subject to geodynamic processes evolutionary effects. It is based on the prediction of isolation properties stability in a structural tectonic block of the Earth’s crust for a given time. The danger is in the possibility that the selected structural block may be broken by new tectonic faults or movements on a passive fault may be activated and thus underground water may penetrate to HLW containers.

Current Status of Radioactive Waste Disposal in Russia

2003 ◽  
Author(s):  
T. A. Gupalo ◽  
V. V. Lopatin ◽  
N. F. Lobanov
Keyword(s):  
Radioactive Waste ◽  
Fuel Cycle ◽  
Radioactive Waste Disposal ◽  
Current Status ◽  
Nuclear Materials ◽  
Potential Hazard ◽  
Research Activity ◽  
Closed Fuel Cycle ◽  
The Russian Federation ◽  
Geological Formations

A huge amount of radioactive waste has been accumulated in the Russian Federation (RF) in the course of implementation of the defense and energy programs, industrial and research activity involving the use of nuclear materials. The most justified and technically feasible technology of solidified RW isolation is its disposition in low-permeable geological formations in specially constructed underground facilities. Today in Russia a Closed Fuel Cycle (CFC) has been adopted, at the CFC final stage the spent nuclear materials and radioactive waste have to be isolated from the biosphere for the whole term of their potential hazard. In Russia, in accordance with the regional approach to the decision of Radioactive Waste (RW) disposal problem, several candidate disposal sites have been assigned.

scholarly journals Calculation of the Height of Capillary Rise of Water in Soils

2020 ◽  
Vol 8 (6) ◽  
pp. 4832-4835
Keyword(s):  
Water Saturation ◽  
Underground Structure ◽  
Capillary Rise ◽  
Soil Layer ◽  
Underground Water ◽  
Wall Material ◽  
Capillary Water ◽  
Temporary Streams ◽  
Filter Water ◽  
Soil Pores

Rain and melt water will form temporary accumulations of surface water on the surface. When they seep into the ground, temporary streams of leaky filter water are formed. If a limited section of water-resistant soil layer or the roof of an underground structure is encountered in the path of these waters, a temporary aquifer-the upper layer of ground water-may form above them. In temporary and permanent aquifers, the soil pores are completely filled with gravitational water, the degree of water saturation is equal to one, and there is pressure under the surface of underground water. Above this surface is a zone of capillary moisture, while the level of capillary rise is determined by the granulometric composition of the soil and ranges from tens of centimeters in sand to several meters in dusty and clay soils. Capillary water rises in the ground on free canals formed by mutually communicating pores, or is kept in them in limbo.The lifting of the liquid in the capillary continues until the gravity acting on the column of the liquid in the capillary becomes equal to the resulting force. Capillary water penetrates from the ground into the walls and rises to a height of up to 2 meters. The normal moisture content of the brick walls is 0.02...0,03, and in the case of unprotected contact with moist soil is increased to 0.15...0.25. On the inside of the walls there is a damp, mildew. Evaporating water increases humidity in the room, and the salts released when it evaporates from salt solutions lead to peeling paint, destruction of plaster and wall material.

The Belgian Demonstration Programme for the Disposal of High-Level and Long-Lived Radioactive Waste

2006 ◽  
Vol 932 ◽  
Author(s):  
Bernier Frédéric ◽  
Demarche Marc ◽  
Bel Johan
Keyword(s):  
Radioactive Waste ◽  
Thermal Load ◽  
Large Scale ◽  
Mechanical Response ◽  
Boom Clay ◽  
Geological Formation ◽  
Important Input ◽  
Clay Layers ◽  
High Level ◽  
Large Scale Tests

ABSTRACTThe EIG EURIDICE is responsible for performing large-scale tests, technical demonstrations and experiments so as to assess the feasibility of a final disposal of vitrified radioactive waste in deep clay layers. This programme is part of the Belgian Research and Development programme managed by ONDRAF/NIRAS. The research infrastructure includes the Underground Research Facilities HADES (URF HADES) in the Boom Clay geological formation and surface facilities. The achievements of the demonstration programme are the demonstration of the construction of shafts and galleries at industrial scale, the characterisation of the hydro-mechanical response of the host rock, and the “OPHELIE mock-up” a large scale hydration test under thermal load of pre-fabricated bentonite blocks. The future works will consist mainly in the realisation of the “PRACLAY experiments” including a large scale heater test. The large scale heater test has to demonstrate that Boom Clay is suitable, in terms of performance of the disposal system, to undergo the thermal load induced by the vitrified waste. The combined effect of the excavation and the thermal load will be investigated. A long term (more than 10 years) large scale heater test would be representative of the most penalizing conditions that could be encountered in the real disposal. The results of this test will constitute an important input for the Safety and Feasibility Cases 1 (SFC-1, 2013) and 2 (SFC-2, 2020).

Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal: Problem and Solutions

2014 ◽  
Vol 1665 ◽  
pp. 3-12 ◽  
Author(s):  
Michael I. Ojovan ◽  
Anthony J. Wickham
Keyword(s):  
Radioactive Waste ◽  
International Atomic Energy Agency ◽  
Waste Disposal ◽  
Atomic Energy ◽  
Individual Member ◽  
Acceptance Criteria ◽  
Energy Agency ◽  
Member States ◽  
Irradiated Graphite ◽  
Disposal Problem

ABSTRACTAn overview is given of an International Atomic Energy Agency Coordinated Research Project (CRP) on the treatment of irradiated graphite (i-graphite) to meet acceptance criteria for waste disposal. Graphite is a unique radioactive waste stream, with some quarter-million metric tons worldwide eventually needing to be disposed of. The CRP has involved 24 organizations from 10 Member States. Innovative and conventional methods for i-graphite characterization, retrieval, treatment and conditioning technologies have been explored in the course of this work, and offer a range of options for competent authorities in individual Member States to deploy according to local requirements and regulatory conditions.

Overview of the JAEA Knowledge Management System Supporting Implementation and Regulation of Geological Disposal in Japan

2009 ◽  
Author(s):  
Hiroyuki Umeki ◽  
Kazumasa Hioki ◽  
Hiroyasu Takase ◽  
Ian McKinley
Keyword(s):  
Knowledge Management ◽  
Radioactive Waste ◽  
Waste Management ◽  
Management System ◽  
Knowledge Management System ◽  
Radioactive Waste Management ◽  
Energy Agency ◽  
Geological Disposal ◽  
Definition Of ◽  
Site Characterisation

The exponential growth in the knowledge base for radioactive waste management is a cause for concern in many national programmes. In Japan, this problem is exacerbated by a volunteering approach to siting of a deep geological repository, which requires particular flexibility in the tailoring of site characterisation plans, repository concepts and associated performance assessments. Recognition of this situation led, in 2005, to initiation by Japan Atomic Energy Agency (JAEA) of an ambitious project to develop an advanced Knowledge Management System (KMS) aimed to facilitate its role as the supplier of background R&D support to both regulators and implementers of geological disposal. This overview outlines the boundary conditions and milestones for the Japanese radioactive waste management programmes, the roles of key organisations and the particular responsibilities of JAEA that led to definition of the goals of the KMS.

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