Abstract
The temperature evolution within a deep geological repository (DGR) is a key design consideration for the safe and permanent storage of the high-level radioactive waste contained inside used nuclear fuel containers (UFCs). Due to the material limitations of engineered components with respect to high temperature tolerance, the Nuclear Waste Management Organization of Canada requires the maximum temperature within a future Canadian DGR to be less than 100 °C. Densely placing UFCs within a DGR is economically ideal, but greater UFC placement density will increase the maximum temperature reached in the repository. This paper was aimed to optimize (i) the separation between UFCs, (ii) the distance between container placement rooms, and (iii) the locations of the age-dependent UFCs in the placement rooms for a conceptual DGR constructed in crystalline rock. Surrogate-based optimization reduced the amount of computationally expensive evaluations of a COMSOL Multiphysics model used to study the temperature evolution within the conceptual DGR and determined optimal repository design points. Via yield optimization, nominal design points that considered uncertainties in the design process were observed. As more information becomes available during the design process for the Canadian DGR, the methods employed in this paper can be revisited to aid in selecting a UFC placement plan and to mitigate risks that may cause repository failure.
Highlights
In accordance with international scientific consensus, the best solution for the final disposal of Canadian high-level radioactive waste, which is predominantly produced by the country’s operation of nuclear power plants running CANDU reactors, is to isolate it within a deep geological repository (DGR) that will prevent radionuclide release into the biosphere for at least one million years
Designing and implementing such a repository are the responsibilities of the Nuclear Waste Management Organization (NWMO), and they have devised a plan for a DGR that will utilize a multiple-barrier system
used nuclear fuel containers (UFCs) arrangements for a Canadian DGR in a crystalline rock environment conceptualized by NWMO were studied
Summary
In accordance with international scientific consensus, the best solution for the final disposal of Canadian high-level radioactive waste, which is predominantly produced by the country’s operation of nuclear power plants running CANDU reactors, is to isolate it within a deep geological repository (DGR) that will prevent radionuclide release into the biosphere for at least one million years. Designing and implementing such a repository are the responsibilities of the Nuclear Waste Management Organization (NWMO), and they have devised a plan for a DGR that will utilize a multiple-barrier system. These phenomena are partially influenced by the presence of groundwater and the dissolved chemical species it would contain at the final DGR site
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