scholarly journals Method for Radioactive Waste Disposal in Underground Mines

2021 ◽  
Vol 15 (2) ◽  
pp. 49-62
Author(s):  
E. V. Kuzmin ◽  
◽  
A. V. Kalakutsky ◽  
A. A. Morozov ◽  
◽  
...  
Keyword(s):  
Rock Mass ◽  
Radioactive Waste ◽  
Radioactive Waste Disposal ◽  
Underground Mines ◽  
Regulatory Requirements ◽  
Paper Briefly ◽  
Geomechanical Properties ◽  
Ore Processing ◽  
Underground Disposal ◽  
State Corporation

This paper presents the key parameters associated with the disposal method used to dispose of radioactive waste (RW) of Class 2 and 3 in abandoned underground mines of PIMCU site assuming additional isolation of RW containers, adjustment of bedrock geomechanical properties and compliance with regulatory requirements. The paper briefly analyzes international practices focused on RW disposal in natural and artificial underground cavities. It provides a comparison between the forecasted volumes of RW generation at the enterprises of the State Corporation Rosatom and the available underground disposal capacity at PIMCU site. It presents the main characteristics of a paste filling manufactured based on materials from uranium ore processing and used as an insulating filler inside the vaults. The paper summarizes the results of operations on rock mass reinforcement based on an injection method. It indicates the key advantages of the proposed method.

An Integrated Safety Assessment System for Near-Surface Disposal of Low- and Intermediate-Level Radioactive Waste in Korea

2003 ◽  
Author(s):  
JooWan Park ◽  
Chang-Lak Kim ◽  
Jin Beak Park ◽  
Eun Yong Lee ◽  
Youn Myoung Lee ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Safety Assessment ◽  
Assessment System ◽  
Intermediate Level ◽  
Radioactive Waste Disposal ◽  
System Level ◽  
Assessment Methodology ◽  
Regulatory Requirements ◽  
Near Surface ◽  
Intermediate Level Radioactive Waste

An integrated safety assessment system to be used for evaluation of near-surface disposal concept has been developed within the framework of safety assessment methodology taken for low- and intermediate-level radioactive waste disposal in Korea. It is to provide an evaluation of the safety of the disposal system in a clear, comprehensive and well-documented manner, and to integrate the results into a defensible package showing reasonable assurance of compliance with regulatory requirements for licensing application. This system is made up of two key components, a system-level safety assessment code and an input database/quality assurance module for safety assessment, which both are interfaced with each other.

Rock Mass Characteristics in Beishan, A Preselected Area for China's High‐Level Radioactive Waste Disposal

2019 ◽  
Vol 93 (2) ◽  
pp. 362-372 ◽  
Author(s):  
Xiang WEI ◽  
Ying GUO ◽  
Hanlie CHENG ◽  
Xiangdong MENG ◽  
Mingqian CHENG ◽  
...  
Keyword(s):  
Rock Mass ◽  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
High Level Radioactive Waste ◽  
High Level

scholarly journals Workshop: Best-practice for laboratory testing low-permeable materials

2021 ◽  
Vol 1 ◽  
pp. 299-300
Author(s):  
Ben Laurich ◽  
Jürgen Hesser ◽  
Sibylle Mayr ◽  
Lisa Winhausen ◽  
Amin Ghanizadeh ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Measurement Errors ◽  
Laboratory Testing ◽  
Best Practice ◽  
Radioactive Waste Disposal ◽  
Low Permeability ◽  
Coupled Flow ◽  
Barrier Material ◽  
Practice Analysis ◽  
Underground Disposal

Abstract. The testing of low-permeable materials is challenging. Yet, for the disposal of radioactive waste, it is essential, too. This workshop is aimed at gathering ambitious scientists to discuss and to collaborate on their experiences in the laboratory testing of low-permeable materials. The focus here is on the methods: What method is best for what kind of low-permeable host rock (salt/clay) and for what kind of technical barrier material (bentonite/crushed salt)? How can measurement errors be correctly determined? What are the crucial “bottlenecks” in the device setups? How can high porous but low permeable samples best be pre-saturated? How can coupled flow and cumbersome gas traps in the tests be dealt with? What is the best-practice analysis of permeability from pressure decay recordings? Is there a hope of defining a standardized procedure for low-permeability testing? These points will be reflected in the light of radioactive waste disposal and in the need to find a best-practice solution when it comes to eventual evaluation and comparison of potential underground disposal sites.

Justification for Possibility to Dispose of Class 2 and 3 Radioactive Waste in Underground Space of Uranium Mines

2020 ◽  
pp. 32-37
Author(s):  
E.V. Kuzmin ◽  
A.V. Kalakutskiy ◽  
M.A. Tarasov ◽  
A.A. Morozov
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Nuclear Power ◽  
Negative Impact ◽  
Radioactive Waste Disposal ◽  
Underground Mines ◽  
Underground Space ◽  
Uranium Deposits ◽  
Nuclear Power Generation ◽  
Intensive Development

Intensive development of the nuclear power generation industry creates the issue of radioactive waste disposal (RAW), which has a negative impact on the environment. Development of uranium deposits using underground mines produces openings, e.g. workings and stopes that can be used as reservoirs for RAW storage. This requires a geomechanical assessment of the condition of mine workings and stopes, evaluation of their total volume, compliance with the requirements for the nuclear waste disposal sites, necessary preparation, as well as evaluation of the limits of existing mining technologies and equipment.

Propagation and Interactions of Acoustic Waves in a Waveguide Attached at the Surface of Rock

2010 ◽  
Author(s):  
Jin-Seop Kim ◽  
Kyung-Soo Lee ◽  
S. Kwon ◽  
Gye-Chun Cho
Keyword(s):  
Rock Mass ◽  
Radioactive Waste ◽  
Acoustic Waves ◽  
Field Application ◽  
Point Of View ◽  
Radioactive Waste Disposal ◽  
Frequency Variation ◽  
Emission Detection

Measurements of the dynamic response of a rock mass are inevitable in the systematic long-term monitoring and the maintenance of the radioactive waste disposal repository. With this point of view, AE (acoustic emission) detection is considered to be a promising technique for monitoring the in-situ performance of a rock mass. In this study, the propagation and interactions of guided acoustic waves in a waveguide connector, which is required in an in-situ application of an AE monitoring system were investigated and the coupling methods of a waveguide to the surface of rock mass were compared. The changes in acoustic wave amplitude, time delay, frequency variation, and system transfer function were measured between the waveguide and a rock sample. Subsequently the waveguide coupling conditions filled with epoxy were compared with a mechanical type of coupling for the validity of field application. The results derived from this study can be valuable information for the quantitative analysis of signal processing in AE source localization and the degree of crack damage in a radioactive waste repository.

scholarly journals Priority parameters of physical processes in a rock mass when determining the safety of radioactive waste disposal

2020 ◽  
Vol 241 ◽  
pp. 118
Author(s):  
V. Gupalo
Keyword(s):  
Rock Mass ◽  
Radioactive Waste ◽  
Waste Disposal ◽  
Radioactive Waste Disposal ◽  
Geological Environment ◽  
Physical Processes ◽  
In Situ Conditions ◽  
Sensitivity Analysis Method ◽  
Geological Formation

Consideration of geodynamic, hydrogeochemical, erosion and other quantitative characteristics describing evolutionary processes in a rock mass is carried out when choosing a geological formation for the disposal of radioactive waste. However, the role of various process parameters is not equal for safety ensuring and additional percentages of measurement accuracy are far from always being of fundamental importance. This makes it necessary to identify various types of indicators of the geological environment that determine the safety of radioactive waste disposal for their detailed study in the conditions of the burial site.An approach is proposed to determine the priority indicators of physical processes in the rock mass that determine the safety of disposal of various types of radioactive waste and require increased attention (accuracy, frequency of measurements) when determining in-situ conditions. To identify such factors, we used the sensitivity analysis method that is a system change in the limits of variable values during security modeling in order to assess their impact on the final result and determine the role of various physical processes in ensuring safety.It is shown that the safety of isolation depends on various factors when burying "natural", "short-lived", and "long-lived" groups of nuclides. The factors that greatly affect safety when disposing of radioactive waste of these types are highlighted. The list of parameters of the geological environment that characterize the priority mechanisms of localization of various types of radionuclide contamination during burial and requiring the most detailed determination in full-scale conditions is defined.

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