On persistent primary variables for numerical modeling of gas migration in a nuclear waste repository

2012 ◽  
Vol 17 (2) ◽  
pp. 287-305 ◽  
Author(s):  
Alain Bourgeat ◽  
Mladen Jurak ◽  
Farid Smaï
Keyword(s):  
Numerical Modeling ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Gas Migration ◽  
Waste Repository

scholarly journals Evaluation of Gas Migration and Rock Damage Characteristics for Underground Nuclear Waste Storage Based on a Coupled Model

2018 ◽  
Vol 2018 ◽  
pp. 1-10 ◽  
Author(s):  
Yi Xue ◽  
Faning Dang ◽  
Fang Shi ◽  
Rongjian Li ◽  
Zhengzheng Cao
Keyword(s):  
Nuclear Waste ◽  
Sedimentary Rock ◽  
Damage Model ◽  
Mechanical Damage ◽  
Coupled Model ◽  
Nuclear Waste Repository ◽  
Gas Migration ◽  
Nuclear Waste Storage ◽  
Deformation And Failure ◽  
Waste Repository

In the deep geological repository of nuclear waste, the corrosion of waste generates gas, which increases the storage pressure, changes the properties of the rock strata, and affects the stability of nuclear waste repository. Therefore, it is of great importance to understand the gas migration in the engineering barrier and the potential impact on its integrity for the safety assessment of nuclear waste repository. A hydro-mechanical-damage model for analyzing gas migration in sedimentary rocks is established in this paper. On the basis of which, a set of coupled formulas for the coupling of gas migration in rock mass is established. The model considers the characteristics of gas migration in sedimentary rock, especially the microcracks caused by the degradation of elastic modulus and damage, and the coupling between the rock deformation and failure of fractures. The numerical simulation of gas injection test is beneficial to understand the mechanism of gas migration process in sedimentary rock.

Chemical, Physical and Engineering Characterization Of Candidate Backfill Clays and Clay Admixtures for a Nuclear Waste Respository-Part I

1981 ◽  
Vol 6 ◽  
Author(s):  
Sudesh K. Singh
Keyword(s):  
Nuclear Waste ◽  
Morphological Changes ◽  
Deionized Water ◽  
Engineering Properties ◽  
Nuclear Waste Repository ◽  
Exchange Cation ◽  
Mineral Components ◽  
Waste Repository ◽  
Mineralogical Compositions

ABSTRACTFourteen Canadian clays and clay admixtures were subjected to simulated nuclear waste repository environments. The present work is concerned with the montmorillonite-dominant materials only. The montmorillonite-dominant samples showed significant leaching on interaction with deionized water. On heating the samples at 200°C for 500 hours, montmorillomites lost intermicellar water completely and acquired cusp-like to cylindrical morphologies. The loss of water and the morphological changes in montmorillonites significantly altered the engineering characteristics. Permeability, shrinkage limits, compactability and shear strength varied in response to the dominant exchange cation in the structure of montmorillonites and the presence of other mineral components in the materials. The synthetic granite water reacted with montmorillonites and led to changes in chemical and mineralogical compositions, crystalline state and engineering properties.

Sign in / Sign up

Export Citation Format

Share Document