Thermal and physical properties of candidate buffer–backfill materials for a nuclear fuel waste disposal vault

1989 ◽  
Vol 26 (4) ◽  
pp. 629-639 ◽  
Author(s):  
H. S. Radhakrishna ◽  
H. T. Chan ◽  
A. M. Crawford ◽  
K. C. Lau
Keyword(s):  
Hydraulic Conductivity ◽  
Nuclear Fuel ◽  
Waste Disposal ◽  
Management Program ◽  
Buffer Material ◽  
Backfill Materials ◽  
And Performance ◽  
Nuclear Fuel Waste ◽  
Clay Barriers ◽  
Ontario Hydro

As part of the Canadian Nuclear Fuel Waste Management Program, Ontario Hydro has, over several years, conducted research into the behaviour and performance of buffer–backfill for the proposed nuclear fuel waste disposal vault. In this paper, a review has been made of laboratory studies made at Ontario Hydro on the thermal properties, strength, hydraulic conductivity, and compactability of clay-based buffer materials. The results of this work have enabled the formulation of selection criteria for the buffer material mix for the prototype Canadian nuclear fuel waste disposal scheme. Key words: bentonites, buffer, backfill, nuclear waste disposal, thermal conductivity, clays, hydraulic conductivity, compaction, clay barriers, clay seals, shrinkage.

Materials Research for the Canadian Nuclear Fuel Waste Management Program

1981 ◽  
Vol 6 ◽  
Author(s):  
Donald J. Cameron
Keyword(s):  
Nuclear Fuel ◽  
Waste Disposal ◽  
Hard Rock ◽  
Technology Development ◽  
Management Program ◽  
Materials Research ◽  
Backfill Materials ◽  
Nuclear Fuel Waste ◽  
Irradiated Fuel ◽  
Selection Of

ABSTRACTNuclear fuel waste disposal research in Canada is concentrating on hard-rock disposal. The research programs concerned with the man-made components of the disposal system are reviewed. Irradiated fuel and solidified reprocessing wastes are both being researched, as are durable containers, and buffer and backfill materials. This review concentrates mainly on the more scientific aspects of the research, which contribute to the selection of preferred options for the various components of the system, and which support directly or indirectly the safety analysis of the disposal concept. Some technology development is included in the program now, and this is expected to expand as confidence in the acceptability of the disposal concept grows.

A Review of Progress in the Canadian Nuclear Fuel Waste Management Program

1985 ◽  
Vol 50 ◽  
Author(s):  
R. B. Lyon ◽  
L. H. Johnson
Keyword(s):  
Waste Management ◽  
Nuclear Fuel ◽  
Management Program ◽  
Selection Methods ◽  
Transportation Fuel ◽  
Waste Immobilization ◽  
Fuel Storage ◽  
And Performance ◽  
Nuclear Fuel Waste ◽  
Made In

AbstractThe Canadian Nuclear Fuel Waste Management Program is reviewed, illustrating the progress that has been made in assessing the concept of disposal of nuclear fuel waste in plutonic rock of the Canadian Shield. Research is being conducted into used fuel storage and transportation, fuel waste immobilization, site characterization and selection methods, and performance assessment modelling. Details of achievements in these areas are outlined, and results of the most recent interim assessment are discussed.

The geochemical environment of nuclear fuel waste disposal

1996 ◽  
Vol 42 (4) ◽  
pp. 401-409 ◽  
Author(s):  
M. Gascoyne
Keyword(s):  
Nuclear Fuel ◽  
Waste Disposal ◽  
Canadian Shield ◽  
Geochemical Environment ◽  
Research Areas ◽  
Reducing Conditions ◽  
Backfill Materials ◽  
The Stability ◽  
Underground Research Laboratory ◽  
Nuclear Fuel Waste

The concept for disposal of Canada's nuclear fuel waste in a geologic environment on the Canadian Shield has recently been presented by Atomic Energy of Canada Limited (AECL) to governments, scientists, and the public, for review. An important part of this concept concerns the geochemical environment of a disposal vault and includes consideration of rock and groundwater compositions, geochemical interactions between rocks, groundwaters, and emplaced vault materials, and the influences and significance of anthropogenic and microbiological effects following closure of the vault. This paper summarizes the disposal concept and examines aspects of the geochemical environment. The presence of saline groundwaters and reducing conditions at proposed vault depths (500–1000 m) in the Canadian Shield has an important bearing on the stability of the used nuclear fuel, its container, and buffer and backfill materials. The potential for introduction of anthropogenic contaminants and microbes during site investigations and vault excavation, operation, and sealing is described with examples from AECL's research areas on the Shield and in their underground research laboratory in southeastern Manitoba. Keywords: nuclear waste disposal, geochemistry, Canadian Shield, groundwater chemistry.

Modelling the Consumption of Oxygen by Container Corrosion and Reaction with Fe(II)

1995 ◽  
Vol 412 ◽  
Author(s):  
M. Kolář ◽  
F. King
Keyword(s):  
Nuclear Fuel ◽  
Waste Disposal ◽  
Corrosion Reaction ◽  
Crushed Granite ◽  
Backfill Materials ◽  
Nuclear Fuel Waste ◽  
Oxidation Of Organics

AbstractA model is described that predicts the rate of O2 consumption in a sealed nuclear fuel waste disposal vault as a result of container corrosion, reaction with biotite and the oxidation of organics and other oxidizable impurities in the clay. The most important reactions leading to the consumption of O2 for Cu containers in a conceptual Canadian disposal vault are container corrosion, the oxidation of dissolved Cu(I) and the oxidation of organics and other impurities in the clay. Consumption of O2 by the oxidation of dissolved Fe(II) from biotite is significant in backfill materials containing crushed granite and in the rock itself. The O2 initially trapped in the disposal vault is predicted to be consumed in between 50 and 670 a.

Formulation of backfill material for a nuclear fuel waste disposal vault

1986 ◽  
Vol 23 (2) ◽  
pp. 216-228 ◽  
Author(s):  
Raymond N. Yong ◽  
Prapote Boonsinsuk ◽  
Gary Wong
Keyword(s):  
Hydraulic Conductivity ◽  
Nuclear Fuel ◽  
Clay Content ◽  
Potential Candidate ◽  
Lake Agassiz ◽  
Backfill Material ◽  
Buffer Material ◽  
Swelling Capacity ◽  
Crushed Granite ◽  
Nuclear Fuel Waste

The Canadian concept for disposing of nuclear fuel waste, currently being studied by Atomic Energy of Canada Limited (AECL) and Ontario Hydro, is to permanently place the waste in an underground vault located in plutonic rock of the Canadian Shield at a depth of 500–1000 m. The waste will be in containers surrounded by a buffer material. Following waste emplacement, the vault will be backfilled. The quantity of backfill material required will be between 5 and 10 million cubic metres.The development of backfill material for a nuclear fuel waste vault is directed at determining the appropriate composition of backfill material that will meet the stringent criteria to be set by AECL to ensure its successful performance. The criteria, with respect to engineering behaviour, include low hydraulic conductivity, sufficient swelling capacity upon wetting, low shrinkage upon drying, and low segregation tendency. The methodology adopted and the results obtained are described in this paper. Using a mixture of crushed granite aggregate and glacial Lake Agassiz clay, a potential candidate for backfill material would have a maximum grain size of 19.1 mm and a clay content of at least 25% by weight. Such a backfill material will yield low hydraulic conductivity (close to that of the pure clay) and other properties well within the acceptable range. Key words: aggregate–clay mixture, swelling clay, hydraulic conductivity, backfill, waste management.

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