scholarly journals The role of interfaces in the bentonite barrier of a nuclear waste repository on gas transport

2021 ◽  
Vol 286 ◽  
pp. 106087
Author(s):  
María Victoria Villar ◽  
Beatriz Carbonell ◽  
Pedro Luis Martín ◽  
Carlos Gutiérrez-Álvarez
Keyword(s):  
Nuclear Waste ◽  
Gas Transport ◽  
Nuclear Waste Repository ◽  
Waste Repository

The Role of the Actinides in a Performance Assessment of a Nuclear Waste Repository. SKB's Supporting Actinide Research

2010 ◽  
Vol 1265 ◽  
Author(s):  
Lars Werme ◽  
Sergei Butorin ◽  
Peter M Oppeneer
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Waste ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Performance Assessments ◽  
Nuclear Waste Repository ◽  
Geologic Repository ◽  
Activation Products ◽  
Waste Repository

AbstractAfter a few hundred years, the actinides will dominate the radiotoxicity of spent nuclear fuel. This does not necessarily mean that the actinides will dominate the dose to organisms at the surface above a geologic repository. Quite the contrary, in most performance assessments this dose is dominated by long-lived fission products, activation products and, in the very long perspective, actinide daughters.This makes the far-field migration properties of the actinides less interesting for further research. There are, however, other aspects of the presence of actinides in spent nuclear fuel and some of these and SKB's research in these fields is presented and discussed here.

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.

Modelling of thermal rock mass properties at the potential sites of a Swedish nuclear waste repository

2009 ◽  
Vol 46 (6) ◽  
pp. 1042-1054 ◽  
Author(s):  
Jan Sundberg ◽  
Pär-Erik Back ◽  
Rolf Christiansson ◽  
Harald Hökmark ◽  
Märta Ländell ◽  
...  
Keyword(s):  
Rock Mass ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Rock Mass Properties ◽  
Mass Properties ◽  
Waste Repository

An analytical solution of temperature in a nuclear waste repository

2021 ◽  
Vol 163 ◽  
pp. 108535
Author(s):  
Yao Xue ◽  
De'an Sun ◽  
Lei Wang
Keyword(s):  
Analytical Solution ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Waste Repository

Erratum: “A Review of Corrosion of Titanium Grade 7 and Other Titanium Alloys in Nuclear Waste Repository Environments” (Vol. 61, No. 10, p. 987–1,003)

CORROSION ◽  
2005 ◽  
Vol 61 (11) ◽  
pp. 1107-1107
Author(s):  
F. Hua ◽  
K. Mon ◽  
P. Pasupathi ◽  
G. Gordon ◽  
D. Shoesmith
Keyword(s):  
Titanium Alloys ◽  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Waste Repository ◽  
Titanium Grade
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