Permeability of rock samples from the Kola and KTB superdeep boreholes at high P-T parameters as related to the problem of underground disposal of radioactive waste

2005 ◽  
Vol 240 (1) ◽  
pp. 153-164 ◽  
Author(s):  
A. V. Zharikov ◽  
V. I. Malkovsky ◽  
V. M. Shmonov ◽  
V. M. Vitovtova
Keyword(s):  
Radioactive Waste ◽  
Rock Samples ◽  
Underground Disposal

A Review of Corrosion Considerations of Container Materials Relevant to Underground Disposal of High-Level Radioactive Waste in Belgium

2006 ◽  
Vol 932 ◽  
Author(s):  
Bruno Kursten ◽  
Frank Druyts
Keyword(s):  
Radioactive Waste ◽  
Large Scale ◽  
General Corrosion ◽  
Spent Fuel ◽  
High Level Radioactive Waste ◽  
Boom Clay ◽  
Nuclear Site ◽  
In Situ Experiments ◽  
Underground Disposal ◽  
High Level

ABSTRACTThe underground formation that is currently being considered in Belgium for the permanent disposal of high-level radioactive waste and spent fuel is a 30-million-year-old argillaceous sediment (Boom Clay layer). This layer is located in the northeast of Belgium and extending under the Mol-Dessel nuclear site at a depth between 180 and 280 meter.Within the concept for geological disposal (multibarrier system), the metallic container is the primary engineered barrier. Its main goal is to contain the radioactive waste and to prevent the groundwater from coming into contact with the wasteform by acting as a tight barrier. The corrosion resistance of container materials is an important aspect in ensuring the tightness of the metallic container and therefore plays an important role in the safe disposal of HLW. The metallic container has to provide a high integrity, i.e. no through-the-wall corrosion should occur, at least for the duration of the thermal phase (500 years for vitrified HLW and 2000 years for spent fuel).An extensive corrosion evaluation programme, sponsored by the national authorities and the European Commission, was started in Belgium in the mid 1980's. The main objective was to evaluate the long-term corrosion performance of a broad range of candidate container materials. In addition, the influence of several parameters, such as temperature, oxygen content, groundwater composition (chloride, sulphate and thiosulphate), γ-radiation, … were investigated. The experimental approach consisted of in situ experiments (performed in the underground research facility, HADES), electrochemical experiments, immersion experiments and large scale demonstration tests (OPHELIE, PRACLAY). Degradation modes considered included general corrosion, localised corrosion (pitting) and stress corrosion cracking.This paper gives an overview of the more relevant experimental results, gathered over the past 25 years, of the Belgian programme in the field of container corrosion.

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.

In Situ Sintering of Waste Forms in an Underground Disposal Environment

2003 ◽  
Vol 807 ◽  
Author(s):  
Michael I. Ojovan ◽  
Fergus G. F. Gibb ◽  
William E. Lee
Keyword(s):  
Radioactive Waste ◽  
Boundary Diffusion ◽  
Ambient Pressure ◽  
Radiation Shielding ◽  
Glass Composite ◽  
Waste Forms ◽  
Management Scheme ◽  
Underground Disposal ◽  
Diffusion Mechanisms

ABSTRACTA waste management scheme is described, which aims to utilise the ambient pressure of a disposal environment, its radiation shielding and extended time of storage to ensure reliable immobilisation of radioactive waste in a glass composite or polycrystalline matrix form. The conditions required for natural sintering of the waste form in the repository are assessed for viscous flow and grain boundary diffusion mechanisms. In situ sintering of materials in the repository creates geochemically stable materials in equilibrium with the disposal environment ensuring a higher degree of safety compared to existing approaches.

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.

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