scholarly journals Michigan International Copper Analogue (MICA) project – current status

2021 ◽  
Vol 1 ◽  
pp. 129-130
Author(s):  
Axel Liebscher ◽  
Heini Reijonen ◽  
Ismo Aaltonen ◽  
Christina Lilja ◽  
Simon Norris ◽  
...  
Keyword(s):  
Metallic Copper ◽  
Point Of View ◽  
Current Status ◽  
Geological Disposal ◽  
Native Copper ◽  
Deep Geological Disposal ◽  
Safety Case ◽  
Assessment Time ◽  
Natural Analogues ◽  
High Level

Abstract. One of the key requirements for the deep geological disposal of high-level nuclear waste is the assessment of its long-term performance and safety (up to 1 Ma). Regarding engineered barrier system materials, such as copper, much of the data available comes from short-term investigations, such as laboratory experiments at different scales. Copper is an important part of many waste packaging and disposal concepts, e.g. KBS-3 developed in Sweden and Finland and Mark II developed in Canada. Natural analogues provide another important way of obtaining understanding on potential repository system behavior. Observations made from the geological systems can be utilized in the safety case, providing information on the assessment time scale. Copper analogue studies (both natural analogues and archaeological analogues) have been reported in the literature and they have been extensively reviewed by various authors (e.g. Miller et al., 2000) and by safety case projects (e.g. Reijonen et al., 2015) within waste management organizations. So far, only a few studies have focussed on the general stability of native copper within its natural media (e.g. Milodowski et al., 2000; Marcos, 2002). Keweenaw native copper occurrences (Lake Superior, USA) have been mentioned as a qualitative source of information (e.g. in Miller et al., 2000); however, data to be used in process-based safety assessments for geological disposal are lacking. These deposits have been mined for a long time and there is a great deal of knowledge related to them as well as samples collected, but no formal review has been made from the geological disposal point of view. The native copper at the Keweenaw area reflects various geological environments from bedrock to sediment and even anthropogenic mine site remnants and geochemical environments (e.g., anoxic vs. oxic, sulphur-free vs. sulphur-bearing). It thus provides a unique complementary data source that will be useful for estimating processes governing behavior of metallic copper. The MICA project phase I systematically collects and reviews the existing literature and data on the Michigan copper analogue sites and available sampling potential. Here, we present the current status of the project.

Radioactive waste management in France: safety demonstration fundamentals

2012 ◽  
Vol 41 (3-4) ◽  
pp. 286-293 ◽  
Author(s):  
G. Ouzounian ◽  
S. Voinis ◽  
F. Boissier
Keyword(s):  
Radioactive Waste ◽  
Heat Generation ◽  
Geological Disposal ◽  
Sequence Of Events ◽  
Main Challenge ◽  
Wide Range ◽  
Deep Geological Disposal ◽  
Safety Case ◽  
High Level ◽  
Geological Timescale

The main challenge in development of the safety case for deep geological disposal is associated with the long periods of time over which high- and intermediate-level long-lived wastes remain hazardous. A wide range of events and processes may occur over hundreds of thousands of years. These events and processes are characterised by specific timescales. For example, the timescale for heat generation is much shorter than any geological timescale. Therefore, to reach a high level of reliability in the safety case, it is essential to have a thorough understanding of the sequence of events and processes likely to occur over the lifetime of the repository. It then becomes possible to assess the capability of the repository to fulfil its safety functions. However, due to the long periods of time and the complexity of the events and processes likely to occur, uncertainties related to all processes, data, and models need to be understood and addressed. Assessment is required over the lifetime of the radionuclides contained in the radioactive waste.

scholarly journals Towards an “Implementing Geological Disposal Technology Platform” in Europe

2009 ◽  
Author(s):  
P. Marjatta Palmu ◽  
Torsten L. Eng
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Radioactive Waste Disposal ◽  
Current Status ◽  
High Level Waste ◽  
Geological Disposal ◽  
Technology Platform ◽  
High Level Radioactive Waste ◽  
Deep Geological Disposal ◽  
High Level

Several European waste management organizations have started the work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community [1] about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste, and other long-lived radioactive wastes. At the same time, the European citizens [2] have a widespread wish for a solution for high-level radioactive waste disposal. A majority of the European countries with nuclear power have active waste management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical, and social challenges related to geological disposal is needed, and the cooperation will be beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. Several decades of research, development and demonstration (RD&D) have been carried out in the field of geological disposal. International opportunities of cooperation and establishing a technology platform were explored in the European Commission co-funded projects like Net.Excel [3] and CARD [4]. According to the CARD project, the majority of the funding for RD&D in waste management comes from the implementing organizations. It is envisaged that a technology platform would enhance European cooperation in this area. The platform intends to constitute a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. After the final workshop of the CARD project in 2008, SKB (Sweden) and Posiva (Finland) were committed to lead the preparation work to set-up the Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). Other implementers from France, Germany, Switzerland, Great Britain, Spain, and Belgium joined en suite. A Vision Document for the IGD-TP is about to be finalized after a wider consultation was carried out in July 2009. The final Vision Document and the platform are launched during November 2009. Simultaneously, the preparation of the Strategic Research Agenda for the technology platform’s joint work starts.

The Treatment of Uncertainty in Performance Assessment and Safety Case Development

2007 ◽  
Author(s):  
D. A. Galson ◽  
A. Khursheed
Keyword(s):  
Sensitivity Analysis ◽  
Performance Assessment ◽  
Conceptual Development ◽  
Geological Disposal ◽  
Deep Geological Disposal ◽  
Safety Case ◽  
The Difference ◽  
Site Characterisation ◽  
High Level ◽  
Case Development

This paper presents the results of a review of the treatment of uncertainty in performance assessment (PA) and safety-case development, carried out as part of the European Commission (EC) project PAMINA (Performance Assessment Methodologies IN Application to Guide the Development of the Safety Case). Information on the treatment of uncertainties was gathered from PAMINA participants and several other organisations using a questionnaire, and via a limited wider review of the literature. The questionnaire responses obtained represent 16 disposal programmes in 13 countries, including all of the countries with advanced programmes to implement deep geological disposal, allowing the review to give wide coverage of global activity. A two-day workshop was held in Brussels in March 2007, in which PAMINA participants reviewed an initial document which summarised the questionnaire results. Work plans were formulated for the remainder of the PAMINA programme. The 16 programmes represented are at diverse phases of maturity: four are at the conceptual development or feasibility stage, seven are at the site selection or site characterisation stage, two are at the licensing stage, one is at the construction stage, one has an operational repository, and one is at the decommissioning/closure stage. There is also wide variation in the development of regulations concerning the treatment of uncertainty for deep geological disposal of radioactive waste, with several countries having no specific regulations. The review indicates that there is a high level of consensus with respect to the nature of uncertainties in PAs and how they should be classified, although this is sometimes masked by variations in terminology and differences in the way uncertainties are treated in programmes. A system of classification is set out in this review, with reference to the nature of uncertainties. The review discusses how the principal classes of uncertainty are treated in PAs and safety cases. While nearly all programmes treat parameter and scenario uncertainties, some do not treat conceptual model uncertainties explicitly. Respondents expressed familiarity with sensitivity-analysis techniques, and clearly understand the difference between these and uncertainty analysis. It is less clear how widespread the use of sensitivity analysis is, especially formal mathematical schemes. Almost no organisations identified uncertainties that may challenge programmes, suggesting a high level of confidence in their ability to site and design deep geological disposal facilities so as to manage uncertainties effectively. However, respondents variously identified the engineered barrier system, the geosphere, the biosphere, and future human intrusion as key sources of uncertainty that require further investigation. Responses on the issue of communicating uncertainties were patchy: some respondents professed to have little experience in this area, whereas others chose not to answer the question. Some restricted themselves to discussing communication with regulators. Only a few programmes have gone as far as commissioning research into different approaches to communicating uncertainty to a variety of stakeholders.

scholarly journals Towards an 'implementing geological disposal technology platform' in Europe

2012 ◽  
Vol 76 (8) ◽  
pp. 3439-3444 ◽  
Author(s):  
M. Palmu ◽  
T. Eng ◽  
T. M. Beattie
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Radioactive Waste Disposal ◽  
Current Status ◽  
High Level Waste ◽  
Geological Disposal ◽  
Technology Platform ◽  
High Level Radioactive Waste ◽  
Deep Geological Disposal ◽  
High Level

AbstractSeveral European waste management organizations have started work on creating a technology platform to accelerate the implementation of deep geological disposal of radioactive waste in Europe. There is an increasing consensus in the international community about geological disposal as the preferred option for solving the long-term management of spent fuel, high-level waste and other longlived radioactive wastes. At the same time, European citizens have a widespread desire for a permanent solution for high-level radioactive waste disposal. A majority of European countries with nuclear power have active waste-management programmes, but the current status and the main challenges of those programmes vary. The most advanced waste management programmes in Europe (i.e. those in Sweden, Finland and France) are prepared to start the licensing process of deep geological disposal facilities within the next decade. Despite the differences between the timing and the challenges of the different programmes, there is a joint awareness that cooperation on the scientific, technical and social challenges related to geological disposal is needed, and that it is beneficial for the timely and safe implementation of the first geological disposal facilities. Such a demonstration of a viable solution for the management of high-level radioactive waste will enhance stakeholder confidence in Europe. It is envisaged that a technology platform would enhance European cooperation in this area. The platform will provide a tool for reducing overlapping work, to produce savings in total costs of research and implementation, and to make better use of existing competence and research infrastructures. From 2008, SKB (Sweden) and Posiva (Finland) led the preparation work to set up the implementing geological disposal of radioactive waste technology platform (IGD-TP). Since then other implementers from France, Germany, Switzerland, United Kingdom, Spain and Belgium have joined the project. To date a strategic research agenda for the platform has been prepared and consulted upon, which is now the basis for taking the platform into a deployment phase.

Durability of potential plutonium wasteforms under repository conditions

2012 ◽  
Vol 76 (8) ◽  
pp. 2911-2918 ◽  
Author(s):  
G. Deissmann ◽  
S. Neumeier ◽  
G. Modolo ◽  
D. Bosbach
Keyword(s):  
Chemical Reactivity ◽  
Final Decision ◽  
Geological Disposal ◽  
Aqueous Environments ◽  
Safety Case ◽  
Key Issues ◽  
The Uk ◽  
High Level ◽  
Radionuclide Release

AbstractSeparated stocks of UK civil plutonium are currently held as a zero value asset in storage, as there is no final decision about whether they should be treated as a resource for future use as nuclear fuel or as waste. Irrespective of future UK government strategies regarding plutonium, at least a portion of the UK civil plutonium inventory will be designated for geological disposal. In this context, we performed a high-level review of the performance of potential wasteforms for the disposal of separated civil plutonium. The key issues considered were the durability and chemical reactivity of the wasteforms in aqueous environments and the long-term radionuclide release under conditions relevant to geological disposal. The major findings of the review, relevant not only to the situation in the UK but to plutonium disposal in general, are summarized in this paper. The review showed that, in the event of a decision being taken to declare plutonium as a waste for disposal, more systematic studies would be required to constrain the wasteform performance under repository conditions in order to derive realistic source terms for a safety case.

Current Status of the Japanese Geological Repository Programme

2007 ◽  
Author(s):  
Kazumi Kitayama
Keyword(s):  
Decision Making ◽  
Project Management ◽  
Radioactive Waste ◽  
Waste Disposal ◽  
Safety Assessment ◽  
Current Status ◽  
Geological Disposal ◽  
Geological Repository ◽  
Deep Geological Disposal ◽  
Site Characterisation

The programme for disposal of radioactive waste in Japan is now moving ahead on a number of fronts. On the regulatory side, responsibility for TRU waste disposal has been assigned to NUMO and guidelines for the safety goals for disposal of LLW have been published. NUMO, as the implementer for the deep geological disposal programme, has been developing the special tools for project management that are needed as a result of the decision to adopt a volunteering approach to siting. NUMO is also building up the technical infrastructure for flexible tailoring of site characterisation, repository design and the associated safety assessment to the conditions found in any volunteer site. This work requires openness and transparency in decision-making but, as several sites may need to be investigated in parallel, particular emphasis is placed on operational practicality.

Key Aspects of the H12 Safety Case

2000 ◽  
Vol 663 ◽  
Author(s):  
Hiroyuki Umeki
Keyword(s):  
Nuclear Fuel ◽  
General Public ◽  
Spent Nuclear Fuel ◽  
Atomic Energy Commission ◽  
Management Program ◽  
Geological Disposal ◽  
Safety Case ◽  
Geological Formation ◽  
High Level ◽  
Key Aspects

ABSTRACTIn Japan, as outlined in the overall high-level radioactive waste (HLW) management program defined by the Japanese Atomic Energy Commission (AEC, 1994), HLW from reprocessing of spent nuclear fuel will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling. It will then be disposed of in a deep geological formation. Pursuant to the overall HLW management program, an organization with responsibility for implementing HLW disposal will be established around the year 2000. This will be followed by site selection and characterization, demonstration of disposal technology, establishment of the necessary legal infrastructure, relevant licensing applications and repository construction, with the objective of starting repository operation by the 2030s and no later than the mid 2040s.The HLW disposal program is currently in the research and development (R&D) phase and the Japan Nuclear Cycle Development Institute (JNC) has been assigned as the leading organization responsible for R&D activities. The aim of the R&D activities at the current stage is to provide a scientific and technical basis for the geological disposal of HLW in Japan and to promote understanding of the safety concept not only in the scientific and technical community but also by the general public. One of the features of the R&D program is that its progress is documented at appropriate intervals, with a view to clearly determining the level of achievement of the program and to promote understanding and acceptance of the geological disposal strategy by the general public. As a major milestone, the Power Reactor and Nuclear Fuel Development Corporation (PNC, now JNC) submitted a first progress report, referred to as H3 (PNC, 1992), in September 1992.

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