CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste

Beijing, China

CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste

Beijing, China
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Ma L.K.,Beijing Research Institute of Uranium Geology | Ma L.K.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Wang J.,Beijing Research Institute of Uranium Geology | Wang J.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | And 3 more authors.
Rock Mechanics: Achievements and Ambitions - Proceedings of the 2nd ISRM International Young Scholars' Symposium on Rock Mechanics | Year: 2012

Rock engineers involved in the design and construction of nuclear waste repositories need to know the permeability of Beishan granite under high stress. A series of permeability tests were performed on specimens of Beishan granite at different axial stress levels and confining stresses. The results indicate that the permeability evolution can be identified in four distinct stages during the test. The permeability decreases during the first stage of loading due to the progressive closure of initial microcracks of rock under compressive stresses. During the second stage, the permeability is nearly constant or slightly increases. In the third stage, there is a significant increase of permeability in this stage in relation with the volumetric dilation. In the fourth phase, the permeability increases to the highest value, and then presents a decreasing trend. © 2012 Taylor & Francis Group.


Ma L.,Beijing Research Institute of Uranium Geology | Ma L.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Ma L.,University of Hong Kong | Li Y.,Beijing Research Institute of Uranium Geology | And 3 more authors.
Applied Mechanics and Materials | Year: 2012

Time-dependent brittle deformation is a foundational process operating in the underground engineering. So, the study of its characterization is essential to the design and construction of excavations in the rocks for high level radioactive waste disposal repositories. In this study, three constant stress tests under different confining pressures were performed on specimens of Beishan granite. Based on the laboratory results, we investigated mechanical creep behavior of Beishan granite under low confining pressures and compared the results with previous investigations. © (2012) Trans Tech Publications, Switzerland.


Xie J.L.,Beijing Research Institute of Uranium Geology | Xie J.L.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Liu Y.M.,Beijing Research Institute of Uranium Geology | Liu Y.M.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Jiang W.J.,China University of Mining and Technology
Rock Mechanics: Achievements and Ambitions - Proceedings of the 2nd ISRM International Young Scholars' Symposium on Rock Mechanics | Year: 2012

A large amount of analysis and studies indicated that bentonite is a possible buffer/backfill material due to its high cation exchange capacity, low permeability, high retention capability of radionuclides, etc. GMZ deposit has been selected as the candidate supplier for buffer material of high-level radioactive wastes (HLW) repository in China. In the work described here, Hot Disk Thermal Constants Analyser was used to measure the thermal conductivity of compacted GMZ001 bentonite. The experimental results were analyzed to evaluate the effects of dry density, water content, and volumetric fraction of soil constituents on the thermal conductivity. Test results demonstrate that the thermal conductivity increases with increasing water content or dry density. A correlation between the thermal conductivity and dry density and water content is proposed to predict the thermal conductivity of GMZ001. The thermal conductivity is strongly correlated with the volumetric fraction of air. A linear correlation between them is presented. © 2012 Taylor & Francis Group.


Zhao J.,Beijing Research Institute of Uranium Geology | Zhao J.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Chen L.,Beijing Research Institute of Uranium Geology | Chen L.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | And 5 more authors.
Engineering Geology | Year: 2016

Gaomiaozi (GMZ) bentonite is currently considered as the most suitable buffer material for high-level radioactive waste geological repository in China. To investigate the long-term performance of GMZ bentonite under repository conditions, a large scale mock-up test has been carried out since 2011. In the test, a hydration system and an electrical heater were employed to simulate the Thermal-Hydro-Mechanical (THM) coupled conditions near a repository. In this work, a numerical study is performed to reproduce the experimental data obtained in the first three years of the China-Mock-up experiment. The principle THM characteristics and parameters of the bentonite are presented. On this basis, a THM coupled constitutive model is introduced. With the proposed model, numerical simulations of the China-Mock-up test are carried out using LAGAMINE. The numerical data of temperature, relative humidity, and swelling pressure of the GMZ compacted bentonite are compared with the experimental ones. We discuss the effect of the balance between the drying effect and water penetration process on the THM behavior of the GMZ bentonite. The good agreement between the predicted and experimental results suggests that the proposed model can reproduce the fundamental behavior of GMZ compacted bentonite under coupled THM conditions. © 2016 Elsevier B.V.


Chen L.,Beijing Research Institute of Uranium Geology | Chen L.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Liu Y.M.,Beijing Research Institute of Uranium Geology | Liu Y.M.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | And 14 more authors.
Engineering Geology | Year: 2014

In this paper, the large scale China-Mock-up test, intended to study the thermal-hydro-mechanical (THM) behavior of Gaomiaozi (GMZ) bentonite under relevant repository condition, is presented. In accordance with the current disposal concept of High-level Radioactive Waste (HLW) disposal in China, the facility is designed as a vertical cylindrical tank, filled with compacted GMZ-bentonite. A heater, which simulates the HLW canister, is placed inside the compacted bentonite blocks and pellets. The installed hydration system on the exterior surface simulates the supply of groundwater. The operational phase started on 1st April 2011. Based on the current recorded experimental data, several aspects are addressed in the paper, including the observed THM behavior of the compacted bentonite, the displacement of the electrical heater, and also the influence of unexpected interruptions of electric power supply. The saturation process of the compacted bentonite is strongly influenced by the competing mechanisms of drying effect induced by the heater and the wetting effect by water penetration. As a result, the desiccation-saturation process was observed in the zone close to the heater. An upward displacement of the heater was also noticed, which verified the potential influence of buffer material on the stability of canister. The experiment is a valuable step in establishing the viability of the reference concept, and making progress in the understanding of the behavior of buffer material under thermal-hydro-mechanical (THM) coupled condition. © 2014.


Liu Y.,Beijing Research Institute of Uranium Geology | Liu Y.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | Ma L.,Beijing Research Institute of Uranium Geology | Ma L.,CNNC Key Laboratory on Geological Disposal of High level Radioactive Waste | And 10 more authors.
Journal of Rock Mechanics and Geotechnical Engineering | Year: 2014

According to the preliminary concept of the high-level radioactive waste (HLW) repository in China, a large-scale mock-up facility, named China-Mock-Up was constructed in the laboratory of Beijing Research Institute of Uranium Geology (BRIUG). A heater, which simulates a container of radioactive waste, is placed inside the compacted Gaomiaozi (GMZ)-Na-bentonite blocks and pellets. Water inflow through the barrier from its outer surface is used to simulate the intake of groundwater. The numbers of water injection pipes, injection pressure and the insulation layer were determined based on the numerical modeling simulations. The current experimental data of the facility are herein analyzed. The experiment is intended to evaluate the thermo-hydro-mechano-chemical (THMC) processes occurring in the compacted bentonite-buffer during the early stage of HLW disposal and to provide a reliable database for numerical modeling and further investigation of engineered barrier system (EBS), and the design of HLW repository. © 2014 Institute of Rock and Soil Mechanics, Chinese Academy of Sciences.

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