scholarly journals MODELLING THE HORIZONTAL VELOCITY FIELD OF THE NIZHNE-KANSK MASSIF ACCORDING TO GNSS OBSERVATIONS

Author(s):  
Alexandr Manevich ◽  
Vladimir Kaftan ◽  
Roman Shevchuk ◽  
Danil Urmanov

Within the boundaries of the Nizhne-Kansk granite-gneiss massif, which directly borders on the Atamanovskiy branch of the Yenisei Ridge, the building of an underground research laboratory for validating the safety of disposal of high-level radioactive waste began in 2019. In 2010, researchers of the Mining and Chemical Combine at Zheleznogorsk and the Geophysical Center, Russian Academy of Sciences, organized a satellite geodetic network within the boundaries of the Nizhne-Kansk massif; this network included 30 GNSS stations intended for observations of modern crustal movements.The purpose of this study is to determine vectors and simulate the field of horizontal modern crustal movements from measurements made in 2010 - 2019. The tasks included: creating a catalogue of displacement data; calculating and estimating horizontal velocities of modern crustal movements, modelling the horizontal velocity field using artificial neural networks, developing a kinematic model of the area and comparing it with geological survey data.As a result, the resulting model was found to be in good agreement with the results of structural-geological and geodynamic studies in the area. The rate of convergence between the Siberian Platform and the West Siberian Plate in the interaction zone of the southern part of the Yenisei Ridge can be estimated as 2-4 mm/year. The movements of the selected area are due to sublatitudinal compression along an azimuth of 100-110 degrees. Within the selected tectonic blocks relatively low rates of modern horizontal movements of the earth's crust were obtained, which confirms the stable geodynamic regime of the structural block hosting the underground research laboratory. Thus, the results of the work demonstrate the possibility of disposal of high-level radioactive waste in the selected structural block. 

2018 ◽  
Vol 482 (1) ◽  
pp. 175-190 ◽  
Author(s):  
Mayumi Jo ◽  
Makoto Ono ◽  
Masashi Nakayama ◽  
Hidekazu Asano ◽  
Tomoko Ishii

AbstractPiping and erosion phenomena are serious problems affecting the integrity of buffer materials, which are an element of engineered barrier systems in the geological disposal of high-level radioactive waste. In this study, the outflow behaviour and the condition of buffer materials are investigated using a test pit drilled into host rock at the Horonobe Underground Research Laboratory to consider countermeasures to contain the outflow of the buffer material. The results are as follows: (1) Piping and erosion phenomena occur irrespective of the injection flow rate. However, when the rate is small, the buffer material is considered to be self-repairing and the outflow of the buffer material can be suppressed. (2) When the injection water contains large amounts of electrolytes, the surface of the buffer material peels off and precipitates, probably decreasing the waterproof performance. (3) Bentonite pellets are likely to be an effective countermeasure against piping and erosion.


Author(s):  
Jean-Michel Hoorelbeke ◽  
Joël Chupeau ◽  
Jean Loubrieu ◽  
Jean-Baptiste Poisson ◽  
Richard Poisson

Abstract The 15 year research on high level and long lived radioactive waste disposal in deep geological formations is being carried out by the ANDRA within the framework of the 1991 law. The status of the research program corresponds to the sinking of the shafts of the Meuse/Haute-Marne Underground Research Laboratory in an argilite layer. A set of preliminary concepts associated to this argillite layer has been studied to help address the issues raised by the feasibility analysis of a potential repository with respect to safety objectives. These concepts deal with transuranic no heat emitting waste, high level vitrified waste and potentially disposed spent fuel. Provision is made for a high level of flexibility, in particular regarding the reversibility of the step by step disposal process. The architecture of the repository concepts distinguishes disposal zones dedicated respectively to transuranic (type B) waste, vitrified high level (type C) waste, UOX and MOX spent fuel (if the case arrises). Each zone is itself divided into modules. The modular design, which segregates the waste categories, guarantees in particular the flexibility of the repository to contend with potential variations in inventory or waste management modes. This makes it possible to study the feasibility of disposal of each type of waste, in an independent way from the others. For each disposal zone and waste category, current studies, including safety and cost analysis, enable to compare various design options of the disposal cells and modules, prior to selecting those which will be presented in 2005. The paper mentions research targets of the program aiming at answering major scientific and technological questions raised by the concepts. The next milestone of the research program is scheduled at the end of the year 2001. It aims at tuning the approach to be used to assess the feasibility of disposal by 2005. The design will progressively benefit from the research carried out in the Meuse/Haute Marne underground research laboratory and other fields: The resulting data make it possible to fit the models used to dimension the structures, especially in the 2002–2005 period.


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