Perspectives on the Review of AECL's Proposal for Disposing of Canada's Nuclear Fuel Waste

1997 ◽  
Vol 506 ◽  
Author(s):  
K.W. Dormuth ◽  
P.A. Gillespie ◽  
S.H. Whitaker

ABSTRACTA federal Environmental Assessment Panel has completed public hearings on the proposed concept for geological disposal of Canada's nuclear fuel waste. The Panel will make recommendations to assist the governments of Canada and Ontario in reaching decisions on the acceptability of the proposed concept and on the steps that must be taken to ensure the safe long-term management of nuclear fuel waste in Canada. It is instructive to review the background to the public hearings, to consider the issues that have been important in the public review, and to reflect on the opposing points of view presented at the hearings.

Author(s):  
Malcolm K. Ross ◽  
Don Hovdebo

Abstract Uranium was initially mined in Canada as a strategic mineral, primarily for export to the United States. Currently, uranium is produced for the global energy market and Saskatchewan is the sole producing province in Canada. Uranium development in Saskatchewan dates from 1953 and in 2000 accounted for 31% of global mine production. In the 1990’s the Saskatchewan Government Environmental Assessment Branch reviewed a new generation of uranium mines with large reserves and extremely high average grades. Technically, the development of these mines has required the development of innovative technologies to manage the environmental and occupational health and safety issues associated with the mining of high-grade uranium ores. While the development of these innovative technologies posed a challenge to science and engineering, the potential environmental impacts and level of public concern associated with the development of the high grade uranium deposits equally challenged the ability of the Province of Saskatchewan’s environmental assessment process to evaluate the acceptability of the proposed mines. During the assessment process a major technical, and public, issue was the decommissioning and long-term management of uranium tailings containing high levels of radionuclide and metal contaminants. While technically decommissioning and reclamation are phases of mining that are considered at the end of mine life, scrutiny of these issues during the assessment process contributed significantly to the public and technical acceptability of the proposed mine developments. The design, construction, operation, decommissioning and reclamation of uranium tailings management facilities for the proposed high-grade mines were subject to critical analysis during the technical and public review phases of the environmental assessment processes. Advances in tailings management design, incorporating innovative in-pit disposal methods capable of isolating decommissioned tailings from local groundwater regimes, presented a technical solution to concerns about long-term tailings containment after decommissioning. Public awareness and acceptance of the proposed mine developments was enhanced by the creation of an independent, public inquiry which ran concurrently with the existing federal and provincial assessment processes. The public inquiry was a critical factor, providing an independent forum where the technical acceptability of the proposed long-term tailings management methodologies was discussed. In retrospect the development of the new mines reflects the successful application of an assessment and review process in that the projects met the tests of technical and public acceptability in a process that was seen to be fair, timely, rigorous and public.


2019 ◽  
Vol 482 (1) ◽  
pp. 1-9
Author(s):  
Simon Norris

AbstractGeological disposal provides the safe long-term management solution for higher-activity radioactive waste. The development of a repository (or geological disposal facility) requires a systematic and integrated approach, taking into account the characteristics of the waste to be emplaced, the enclosing engineered barriers, and the host rock and its geological setting.Clays and clayey material are important in the development of many national geological disposal systems. Clays exhibit many interesting properties, and are proposed both as host rocks and as material for engineered barriers. Whatever their use, clays present various characteristics that make them high-quality barriers to the migration of radionuclides and chemical contaminants. As host rocks, clays are, in addition, hydrogeologically, geochemically and mechanically stable over geological timescales (i.e. millions of years).


Author(s):  
Desiree Sandoica Paris ◽  
Manuel Soler Severino

There are public entities that possess in their hands multiple property assets, that are difficult to manage, being, in many cases, buildings that are considered icons that contribute to the character of their surroundings or that take part of our historical heritage or have some kind of protection. It is difficult for the private sector to manage these assets, if in the public sector, we add the electoral cycle, the problems increase. At a public level, it is more complicated, since it should be understood that the planning of property assets and delivery do not correspond to the political cycles. In addition, policies change once established, perhaps with the development under construction, will inevitably have serious consequences on: the planning, cost and alignment of the building with the final needs of the asset. Therefore, it is important for all the stakeholders to realize that an approach is needed for the long-term management of property asset portfolios. To achieve this goal, we have developed a structured and programmed approach of Property Asset Management adapted to the public sector, in order to provide the best solutions.


1996 ◽  
Vol 465 ◽  
Author(s):  
C. W. Forsberg

ABSTRACTA new repository waste package (WP) concept for spent nuclear fuel (SNF) is being investigated. The WP uses depleted uranium (DU) to improve performance and reduce the uncertainties of geological disposal of SNF. The WP would be loaded with SNF. Void spaces would then be filled with DU (∼0.2 wt % 235U) dioxide (UO2) or DU silicate-glass beads.Fission products and actinides can not escape the SNF UO2 crystals until the UO2 dissolves or is transformed into other chemical species. After WP failure, the DU fill material slows dissolution by three mechanisms: (1) saturation of WP groundwater with DU and suppression of SNF dissolution, (2) maintenance of chemically reducing conditions in the WP that minimize SNF solubility by sacrificial oxidation of DU from the +4 valence state, and (3) evolution of DU to lower-density hydrated uranium silicates. The fill expansion minimizes water flow in the degraded WP. The DU also isotopically exchanges with SNF uranium as the SNF degrades to reduce long-term nuclear-criticality concerns.


1998 ◽  
Vol 121 (2) ◽  
pp. 174-188 ◽  
Author(s):  
Bernd Grambow ◽  
Andreas Loida ◽  
Emmanuel Smailos

2002 ◽  
Vol 713 ◽  
Author(s):  
Christophe Poinssot ◽  
Patrick Lovera ◽  
Marie-Hélène Faure

ABSTRACTUnder the geological disposal conditions, spent nuclear fuel (SNF) is expected to evolve during the first thousands years while being maintained isolated from the biosphere before water comes in. Under those circumstances, several driving forces would lead to the progressive intrinsic SNF transformations within the rod which would basically modify the physical and chemical state of the fuel and the subsequent release of radionuclides in solution. In this paper, we briefly summarize the mechanisms we estimate to be significant and propose a new framework for the quantitative assessment of the radionuclide (RN) inventory we estimate to be associated to the classically referred to “Instant Release Fraction” (IRF). We hence demonstrate that in this framework, significantly high IRF values have to be expected for the long term due mainly to the presence of athermal diffusion processes.


1984 ◽  
Vol 44 ◽  
Author(s):  
M. Onofrei ◽  
D. K. Raine ◽  
L. Brown ◽  
F. Stanchell

AbstractThe leaching behaviour of various ceramics was studied as part of a program to evaluate their potential use as container material for very long term containment of nuclear fuel waste under conditions of deep geologic disposal.Samples of four grades of Al2O3, stabilized ZrO2, TiO2, a cermet (70% A12O3- 30% TiC) and porcelain have been leached in deionized distilled water, Standard Canadian Shield Saline Solution (SCSSS), and SCSSS plus 20% Na-bentonite under static conditions at 100°C for periods up to 120 d.The results of these ongoing leaching experiments suggest that the controlling features of the ceramic leaching process were leachant composition, and the presence and concentration of ions in the solution capable of preferentially precipitating on the ceramic surface, i.e., silicon, Mg2+, Ca2+, etc. Weight losses were determined after leaching. The initial leach rates showed a dependence upon ceramic purity and the processing used to prepare the ceramics, as well as the leachant composition. Also, it was apparent that the decrease of leach rates with time occurred as a result of the ceramic components in the leachant approaching their saturation limits.


Author(s):  
Peter A. Brown

The Nuclear Fuel Waste (NEW) Act is a stand-alone piece of legislation with some 30 articles and without regulations. The Act deals essentially with social, financial and socioeconomic considerations of the long-term management of nuclear fuel waste. It complements the health, environment, safety and security requirements under the Nuclear Safety and Control, Act. The NFW Act provides for 1) the nuclear industry to set up a waste management organization to manage the full long-term waste management activities and to establish trust funds to finance long-term waste management responsibilities; and 2) the waste management organization to submit, for government decision, long-term waste management options within three years of coming into force.


Sign in / Sign up

Export Citation Format

Share Document